UNITED STATES 


NUCLEAR REGULATORY COMMISSION 


WASHINGTON, D.C. 20555-0001 

March 12, 2012 

EA-12-051 


All Power Reactor Licensees and 

Holders of Construction Permits in 

Active or Deferred Status 

SUBJECT: 	 ISSUANCE OF ORDER TO MODIFY LICENSES WITH REGARD TO RELIABLE 

SPENT FUEL POOL INSTRUMENTATION 

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 reliable spent fuel pool 

indications 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 Document 

Access and Management System (ADAMS) Accession No. ML f1186A950). 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 7.1, concerning reliable spent fuel pool instrumentation, was determined to be 

a high-priority action. This Order is based upon the NTTF recommendation. 

During the events in Fukushima, responders were without reliable instrumentation to determine 

water level in the spent fuel pool. This caused concerns that the pool may have boiled dry, 

resulting in fuel damage. Numerous attempts were made to refill the spent fuel pools, which 

diverted resources and attention from other efforts. The events at Fukushima demonstrated the 

confusion and misapplication of resources that can result from beyond-design-basis external 

events when adequate instrumentation is not available. 

The NRC staff has determined that the current fleet of nuclear power plants is safe to continue 

operation. Additionally, the Commission has determined that the enhanced spent fuel pool 

instrumentation required by this Order represents a substantial increase in protection to public 

health and safety. 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 Constructions 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 Mrs. Lisa Regner, Spent Fuel Pool Instrumentation Order 

Project Manager (301-415-1906), 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/enforcement/actions/. The 

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

Si::C/~ 

Eric J. Leeds, Director 

Office of Nucle Reactor Regulation 

Michael . Johnson, Director 

Office of New Reactors 

Enclosure: 

Order (EA-12-051) 

cc: Listserv 
ORDER TO MODIFY LICENSES WITH REGARD TO RELIABLE 


SPENT FUEL POOL INSTRUMENTATION 


EA-12-0S1 


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-12-051 

ORDER MODIFYING LICENSES 


WITH REGARD TO RELIABLE SPENT FUEL POOL INSTRUMENTATION 


(EFFECTIVE IMMEDIATELY) 


I. 

The Licensees and construction permit (CP) holders 1 identified in Attachment 1 to this 

Order hold licenses 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 of Federa/ 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. 

1 CP holders, as used in this Order, includes CPs, in active or deferred status, as identified in 

Attachment 1 to this Order (i.e., Watts Bar, Unit 2; and Bellefonte, Units 1 and 2) 
- 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. 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, 

The Unit 4 spent fuel pool contained the highest heat load of the six units with the full core 

present in the spent fuel pool and the refueling gates installed. However, because Unit 4 had 

been shut down for more than 3 months, the heat load was low relative to that present in spent 

fuel pools immediately following shutdown for reactor refueling. Following the earthquake and 

tsunami, the operators in the Units 3 and 4 control room focused their efforts on stabilizing the 

Unit 3 reactor. During the event, concern grew that the spent fuel was overheating, causing a 
- 3 ­

high-temperature reaction of steam and zirconium fuel cladding generating hydrogen gas. This 

concern persisted primarily due to a lack of readily available and reliable information on water 

levels in the spent fuel pools. Helicopter water drops, water cannons, and cement delivery 

vehicles with articulating booms were used to refill the pools, which diverted resources and 

attention from other efforts. Subsequent analysis determined that the water level in the Unit 4 

spent fuel pool did not drop below the top of the stored fuel and no significant fuel damage 

occurred. The lack of information on the condition of the spent fuel pools contributed to a poor 

understanding of possible radiation releases and adversely impacted effective prioritization of 

emergency response actions by decision makers. 

Following the events at the Fukushima Dai-ichi nuclear power plant, the NRC established 

a senior-level agency task force referred to as the Near-Term Task Force (NTTF). The NTTF 

was tasked with conducting a systematic and methodical review of the NRC regulations and 

processes and determining if the agency should make additional improvements to these 

programs in light of the events at Fukushima Dai-ichi. As a result of this review, the NTTF 

developed a comprehensive set of recommendations, documented in SECY -11-0093, 

"Near-Term Report and Recommendations for Agency Actions Following the Events in Japan," 

dated July 12, 2011. These recommendations were modified by the NRC staff following 

interactions with stakeholders. Documentation of the NRC 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 
- 4 ­

the NRC to implement the recommendations. SECY-11-0124 and SECY-11-0137 established 

the NRC staff's prioritization of the recommendations based upon the potential safety 

enhancements. 

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 

United States. Therefore, continued operation and continued licensing activities do not pose an 

imminent threat to public health and safety. However, the NRC's assessment of new insights 

from the events at Fukushima Dai-ichi leads the NRC staff to conclude that additional 

requirements must be imposed on Licensees and CP holders to increase the capability of nuclear 

power plants to mitigate beyond-design-basis external events. These additional requirements 

represent a substantial increase in the protection of public health and safety. The Commission 

has decided to administratively exempt this Order from applicable provisions of the Backfit Rule, 

10 CFR 50.109, and the issue finality requirements in 10 CFR 52.63 and 10 CFR Part 52, 

Appendix D, Paragraph VIII. 

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 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 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 and CP holders are maintaining an adequate level of public health and safety and 

common defense and security. While compliance with NRC requirements presumptively 
- 5 ­

ensures 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 and 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 public health and safety. 

In the case of spent fuel pools, compliance with existing regulations and guidance 

presumptively provides reasonable assurance of the safe storage of spent fuel. In particular, 

Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 establishes 

the general design criteria (GDC) for nuclear power plants. All currently operating reactors were 

licensed to the GDC or meet the intent of the GDC. The GDC provide the design features of the 

spent fuel storage and handling systems and the protection of these systems from natural 

phenomena and operational events. The accidents considered during licensing of U.S. nuclear 

power plants typically include failure of the forced cooling system and loss of spent fuel pool 

inventory at a specified rate within the capacity of the makeup water system. Further, spent fuel 

pools at U.S. nuclear power plants rely on maintenance of an adequate inventory of water under 

accident conditions to provide containment, as well as the cooling and shielding safety functions. 
During the events in Fukushima, responders were without reliable instrumentation to 

determine water level in the spent fuel pool. This caused concerns that the pool may have boiled 

dry, resulting in fuel damage.2 Fukushima demonstrated the confusion and misapplication of 

resources that can result from beyond-design-basis external events when adequate 

instrumentation is not available. 

The spent fuel pool level instrumentation at U.S. nuclear power plants is typically narrow 

range and, therefore, only capable of monitoring normal and slightly off-normal conditions. 

Although the likelihood of a catastrophic event affecting nuclear power plants and the associated 

spent fuel pools in the United States remains very low, beyond-design-basis external events 

could challenge the ability of existing instrumentation to provide emergency responders with 

reliable information on the condition of spent fuel pools. Reliable and available indication is 

essential to ensure plant personnel can effectively prioritize emergency actions. 

The Commission has determined that the spent fuel pool instrumentation required by this 

Order represents a significant enhancement to the protection of public health and safety and is an 

appropriate response to the insights from the Fukushima Dai-ichi accident While this 

consideration is qualitative in nature, the Commission has long taken the position that the 

determination as to whether proposed backfits represent a substantial safety improvement may 

be qualitative in nature. Staff Requirements Memorandum, SECY-93-086, "Backfit 

Considerations" (June 30, 1993), pp. 1-2. However the Commission does not. at this time, have 

sufficient information to complete a full backfit analysis of the spent fuel pool instrumentation that 

would be required by this Order. The NRC is analyzing the insights gained from the Fukushima 

Dai-ichi accident on an accelerated time line. Additionally, the NRC has considered the 

2 See Institute of Nuclear Power Operations (INPO) 11-005, "Special Report on the Nuclear 

Accident at the Fukushima Daiichi Nuclear Power Station," Revision 0, issued November 2011, 

p.36. 
- 7 ­

Congressional intent that the agency act expeditiously on Tier 1 recommendations. 

The Commission has recognized, in exceptional circumstances, that some proposed rules 

may not meet the requirements specified in the Backfit Rule but nevertheless should be adopted 

by the NRC. Hence, the Commission advised the NRC staff that it would consider, on a 

case-by-case basis, whether a proposed regulatory action should be adopted as an "exception" to 

the Backfit Rule. This Order represents such a case. Therefore, the Commission has decided 

to administratively exempt this Order from the Backfit Rule and the issue finality requirements in 

10 CFR 52.63 and 10 CFR Part 52, Appendix D, paragraph VIII for several reasons. 

The Fukushima Dai-ichi accident was unprecedented in terms of initiating cause and the 

particular failure sequence. In addition, our review of this event has highlighted the benefits that 

can be derived from the availability of more diverse instrumentation. Consistent with the final 

Aircraft Impact Assessment Rule, 10 CFR 50.150,74 FR 28112 (June 12, 2009), the 

Commission's decision to administratively exempt this Order from compliance with the Backfit 

Rule is a highly exceptional action limited to the insights associated with the extraordinary 

underlying circumstances of the Fukushima Dai-ichi accident and the NRC's lessons learned. 

Furthermore, the extensive stakeholder engagement and broad endorsement for timely action 

support the Commission's judgment that immediate action to commence implementation of the 

spent fuel monitoring requirements is warranted at this time. 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. 

Based upon the considerations set forth above, the Commission has determined that all 

power reactor licensees and CP holders must have a reliable means of remotely monitoring 

wide-range spent fuel pool levels to support effective prioritization of event mitigation and 

recovery actions in the event of a beyond-design-basis external event. These new requirements 
- 8 ­

provide a greater capability, consistent with the overall defense-in-depth philosophy, and 

therefore greater assurance of protection of public health and safety from the challenges posed 

by beyond-design-basis external events to power reactors. Accordingly, the Commission 

concludes that all operating reactor licensees 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 Part 52 identified in Attachment 1 to this Order shall be 

modified to include the requirements identified in Attachment 3 to this Order. 

IV. 

Accordingly, pursuant to Sections 161 b, 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 CP 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 
- 9 -

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 impact, the 

basis for its determination that the requirement has an adverse impact, and either 

a proposal for achieving the same objectives specified in the Attachment 2 or 

Attachment 3 requirement in question, or a schedule for modifying the facility to 

address the adverse condition. If neither approach is appropriate, the Licensee 
- 10 ­

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 CP holders shall provide an initial status report sixty (GO) days 

after the issuance of the finallSG, and at six (G)-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 holder 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. 
- 11 ­

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 twenty (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 
- 12 ­

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 bye-mail at 

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

which allows the participant (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 htto://www.nrc.oov/site-he/oJe-submitta/siapp/y-certificates.html. System req uirements for 

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

which is available on the agency's public Web site at 

http://www.nrc.gov/site-he/oJesubmitta/s.html. Participants may attempt to use other software 

not listed on the web site, but should note that the NRC's E-Filing system does not support 

unlisted software, and the NRC Meta System Help Desk will not be able to offer assistance in 

using unlisted software. 

If a participant is electronically submitting a document to the NRC in accordance with the 

E-Filing rule, the participant must file the document using the NRC's online, web-based 

submission form. In order to serve documents through the Electronic Information Exchange, 

users will be required to install a web browser plug-in from the NRC web site. Further information 
- 13 ­

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.qov/site-helplesubmitta/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 

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-FiHng 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-helple-submitta/s.htm/.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 
- 14 ­

initial paper filing requesting authorization to continue to submit documents in paper format. 

Such filings must be submitted by: (1) first class mail addressed to the Office of the Secretary of 

the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 

Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to 

the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, 

Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a 

document in this manner are responsible for serving the document on all other participants. 

Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, 

express mail, or expedited delivery service upon depositing the document with the provider of the 

service. A presiding officer, having granted an exemption request from using E-Filing, may 

require a participant or party to use E-Filing if the presiding officer subsequently determines that 

the reason for granting the exemption from use of E-Filing no longer exists. 

Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing 

docket, which is available to the public at http://ehd.nrc.govIEHD 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). 
- 15 ­

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 

Offic 

Ec:.L~ f Nu r Reactor Regulation 

Michael . Johnson, Director 

Office of New Reactors 

Dated this 12th day of March 2012 
POWER REACTOR LICENSEES AND LICENSEES 


WITH ACTIVE AND/OR DEFERRED CONSTRUCTION PERMITS 


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 

Exeion 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 

Fiorida 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 Pubiic 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. I\lPF-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 

RE. 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 

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 N'o. 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-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 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 

Virqil 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 and 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. Box 411 

Burlington, KS 66839 
REQUIREMENTS FOR RELIABLE SPENT FUEL POOL LEVEL 


INSTRUMENTATION AT OPERATING REACTOR SITES AND 


CONSTRUCTION PERMIT HOLDERS 


All licensees identified in Attachment 1 to this Order shall have a reliable indication of the water 

level in associated spent fuel storage pools capable of supporting identification of the following 

pool water level conditions by trained personnel: (1) level that is adequate to support operation 

of the normal fuel pool cooling system, (2) level that is adequate to provide sUbstantial radiation 

shielding for a person standing on the spent fuel pool operating deck, and (3) level where fuel 

remains covered and actions to implement make-up water addition should no longer be deferred. 

1. 	 The spent fuel pool level instrumentation shall include the following design features: 

1.1 	 Instruments: The instrumentation shall consist of a permanent, fixed primary 

instrument channel and a backup instrument channel. The backup instrument 

channel may be fixed or portable. Portable instruments shall have capabilities 

that enhance the ability of trained personnel to monitor spent fuel pool water level 

under conditions that restrict direct personnel access to the pool, such as partial 

structural damage, high radiation levels, or heat and humidity from a boiling pool. 

1.2 	 Arrangement: The spent fuel pool level instrument channels shall be arranged in 

a manner that provides reasonable protection of the level indication function 

against missiles that may result from damage to the structure over the spent fuel 

pool. This protection may be provided by locating the primary instrument channel 

and fixed portions of the backup instrument channel, if applicable, to maintain 

instrument channel separation within the spent fuel pool area, and to utilize 

inherent shielding from missiles provided by existing recesses and corners in the 

spent fuel pool structure. 

1.3 	 Mounting: Installed instrument channel equipment within the spent fuel pool shall 

be mounted to retain its design configuration during and following the maximum 

seismic ground motion considered in the design of the spent fuel pool structure. 

1.4 	 Qualification: The primary and backup instrument channels shall be reliable at 

temperature, humidity, and radiation levels consistent with the spent fuel pool 

water at saturation conditions for an extended period. This reliability shall be 

established through use of an augmented quality assurance process (e.g., a 

process similar to that applied to the site fire protection program). 

1.5 	 Independence: The primary instrument channel shall be independent of the 

backup instrument channel. 

1.6 	 Power supplies: Permanently installed instrumentation channels shall each be 

powered by a separate power supply. Permanently installed and portable 

instrumentation channels shall provide for power connections from sources 

independent of the plant ac and dc power distribution systems, such as portable 

generators or replaceable batteries. Onsite generators used as an alternate 

power source and replaceable batteries used for instrument channel power shall 

have sufficient capacity to maintain the level indication function until offsite 

resource availability is reasonably assured. 

Attachment 2 
- 2 ­

1.7 	 Accuracy: The instrument channels shall maintain their designed accuracy 

following a power interruption or change in power source without recalibration. 

1.8 	 Testing: The instrument channel design shall provide for routine testing and 

calibration. 

1.9 	 Display: Trained personnel shall be able to monitor the spent fuel pool water level 

from the control room, alternate shutdown panel, or other appropriate and 

accessible location. The display shall provide on-demand or continuous 

indication of spent fuel pool water level. 

2. 	 The spent fuel pool instrumentation shall be maintained available and reliable through 

appropriate development and implementation of the following programs: 

2.1 	 Training: Personnel shall be trained in the use and the provision of alternate 

power to the primary and backup instrument channels. 

2.2 	 Procedures: Procedures shall be established and maintained for the testing, 

calibration, and use of the primary and backup spent fuel pool instrument 

channels. 

2.3 	 Testing and Calibration: Processes shall be established and maintained for 

scheduling and implementing necessary testing and calibration of the primary and 

backup spent fuel pool level instrument channels to maintain the instrument 

channels at the deSign accuracy. 
REQUIREMENTS FOR RELIABLE SPENT FUEL POOL LEVEL 


INSTRUMENTATION AT COMBINED LICENSE HOLDER REACTOR SITES 


Attachment 2 to this Order for Part 50 Licensees requires reliable indication of the water level in 

associated spent fuel storage pools capable of supporting identification of the following pool water 

level conditions by trained personnel: (1) level that is adequate to support operation of the 

normal fuel pool cooling system, (2) level that is adequate to provide sUbstantial radiation 

shielding for a person standing on the spent fuel pool operating deck, and (3) level where fuel 

remains covered and actions to implement make-up water addition should no longer be deferred. 

The design bases of Vogtle Units 3 and 4 address many of these attributes of spent fuel pool level 

instrumentation. 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 AP1000 certified design largely addresses the requirements in Attachment 2 by providing two 

safety-related spent fuel pool level instrument channels. The instruments measure level from 

the top of the spent fuel pool to the top of the fuel racks to address the range requirements listed 

above. The safety-related classification provides for the following additional design features: 

• Seismic and environmental qualification of the instruments 

• Independent power supplies 

• Electrical isolation and physical separation between instrument channels 

• Display in the control room as part of the post-accident monitoring instrumentation 

• Routine calibration and testing 

As such, this Order requires Vogtle Units 3 and 4 to address the following requirements that were 

not specified in the certified design. 

1. 	 The spent fuel pool level instrumentation shall include the following design features: 

1.1 	 Arrangement: The spent fuel pool level instrument channels shall be arranged in 

a manner that provides reasonable protection of the level indication function 

against missiles that may result from damage to the structure over the spent fuel 

pool. This protection may be provided by locating the safety-related instruments 

to maintain instrument channel separation within the spent fuel pool area, and to 

utilize inherent shielding from missiles provided by existing recesses and corners 

in the spent fuel pool structure. 

1.2 	 Qualification: The level instrument channels shall be reliable at temperature, 

humidity, and radiation levels consistent with the spent fuel pool water at 

saturation conditions for an extended period. 

1.3 	 Power supplies: Instrumentation channels shall provide for power connections 

from sources independent of the plant alternating current (ac) and direct current 

(dc) power distribution systems, such as portable generators or replaceable 

batteries. Power supply designs should provide for quick and accessible 

connection of sources independent of the plant ac and dc power distribution 

systems. Onsite generators used as an alternate power source and replaceable 

batteries used for instrument channel power shall have sufficient capacity to 

maintain the level indication function until offsite resource availability is reasonably 

assured. 

Attachment 3 
1.4 	 Accuracy: The instrument shall maintain its designed accuracy following a power 

interruption or change in power source without recalibration. 

1.5 	 Display: The display shall provide on-demand or continuous indication of spent 

fuel pool water level. 

2. 	 The spent fuel pool instrumentation shall be maintained available and reliable through 

appropriate development and implementation of a training program. Personnel shall be 

trained in the use and the provision of alternate power to the safety-related level 

instrument channels. 
All Power Reactor Licensees and 

Holders of Constructions 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 Mrs. Lisa Regner, Spent Fuel Pool Instrumentation Order 

Project Manager (301-415-1906), 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 Register for publication. 

Sincerely, 

/raj 

Eric J. Leeds, Director 

Office of Nuclear Reactor Regulation 

/raj 

Michael R. Johnson, Director 

Enclosure: 


Order (EA-12-051) 


cc: Listserv 

Distribution: See next page 

ADAMS A ccesslon N0.: ML 12054A682 ( pac age e-mal k * ·1 concurrence

OFFICE PM: NRR/JLD LA: NRR/JLD QTE* BC: NRR/JLD OGC* 

NAME LRegner SRohrer JDo~ghtery RPascarelli CSafford 

DATE 03/09/2012 03/12/2012 02/05/2012 03/11/2012 03/10/2012 

OFFICE OE* D: JLD* aD: NRO aD: NRR 

NAME RZimmerman 

(NHilton for) 

DSkeen MJohnson ELeeds 

DATE 03/09/2012 03/11/2012 03/12/2012 03/12/2012 

OFFICIAL RECORD COpy