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ATTACHMENT 1—GENERAL TARGET SCHEDULE FOR PROCESSING AND RESOLVING REQUESTS FOR ACCESS TO SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATION AND SAFEGUARDS INFORMATION IN THIS PROCEEDING—Continued

Day Event/Activity

190 ...... (Receipt +180) If NRC staff finds standing, need to know for SGI, and trustworthiness and reliability, deadline for NRC staff to file motion for Protective Order and draft Non-disclosure Affidavit (or to make a determination that the proposed recipient of SGI is not trustworthy or reliable). Note: Before the Office of Administration makes an adverse determination regarding access to SGI, the proposed recipient must be provided an opportunity to correct or explain information. 205 ...... Deadline for petitioner to seek reversal of a final adverse NRC staff trustworthiness or reliability determination either before the pre- siding officer or another designated officer under 10 CFR 2.705(c)(3)(iv). A ...... If access granted: Issuance of presiding officer or other designated officer decision on motion for protective order for access to sen- sitive information (including schedule for providing access and submission of contentions) or decision reversing a final adverse de- termination by the NRC staff. A + 3 ...... Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI and/or SGI consistent with decision issuing the protective order. A + 28 .... Deadline for submission of contentions whose development depends upon access to SUNSI and/or SGI. However, if more than 25 days remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as established in the notice of hearing or opportunity for hearing), the petitioner may file its SUNSI or SGI contentions by that later deadline. A + 53 .... (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI and/or SGI. A + 60 .... (Answer receipt +7) Petitioner/Intervenor reply to answers. >A + 60 .. Decision on contention admission.

[FR Doc. 2012–6541 Filed 3–16–12; 8:45 am] arrangements can be made. Thirty-five Dated: March 7, 2012. BILLING CODE 7590–01–P hard copies of each presentation or Cayetano Santos, handout should be provided to the DFO Chief, Reactor Safety Branch, Advisory thirty minutes before the meeting. In Committee on Reactor Safeguards. NUCLEAR REGULATORY addition, one electronic copy of each [FR Doc. 2012–6543 Filed 3–16–12; 8:45 am] COMMISSION presentation should be emailed to the BILLING CODE 7590–01–P Advisory Committee on Reactor DFO one day before the meeting. If an Safeguards (ACRS), Meeting of the electronic copy cannot be provided within this timeframe, presenters NUCLEAR REGULATORY ACRS Subcommittee on Planning and COMMISSION Procedures; Notice of Meeting should provide the DFO with a CD containing each presentation at least [EA–12–051; NRC–2012–0067; Docket Nos. The ACRS Subcommittee on Planning thirty minutes before the meeting. and Procedures will hold a meeting on (as shown in Attachment 1), License Nos. Electronic recordings will be permitted (as shown in Attachment 1), or April 11, 2012, Room T–2B3, 11545 only during those portions of the Construction Permit Nos. (as shown in Rockville Pike, Rockville, Maryland. meeting that are open to the public. Attachment 1)] The entire meeting will be open to Detailed procedures for the conduct of public attendance, with the exception of and participation in ACRS meetings In the Matter of All Power Reactor a portion that may be closed pursuant were published in the Federal Register Licensees and Holders of Construction to 5 U.S.C. 552b (c)(2) and (6) to discuss Permits in Active Or Deferred Status: on October 17, 2011, (76 FR 64126– organizational and personnel matters Order Modifying Licenses With Regard 64127). that relate solely to the internal To Reliable Spent Fuel Pool personnel rules and practices of the Information regarding changes to the Instrumentation (Effective ACRS, and information the release of agenda, whether the meeting has been Immediately) which would constitute a clearly canceled or rescheduled, and the time unwarranted invasion of personal allotted to present oral statements can I privacy. be obtained by contacting the identified The Licensees and construction The agenda for the subject meeting DFO. Moreover, in view of the permit (CP) holders1 identified in shall be as follows: possibility that the schedule for ACRS Attachment 1 to this Order hold licenses Wednesday, April 11, 2012—11 a.m. meetings may be adjusted by the issued by the U.S. Nuclear Regulatory Until 12 p.m. Chairman as necessary to facilitate the Commission (NRC or Commission) authorizing operation and/or The Subcommittee will discuss conduct of the meeting, persons planning to attend should check with construction of nuclear power plants in proposed ACRS activities and related accordance with the Atomic Energy Act matters. The Subcommittee will gather the DFO if such rescheduling would result in a major inconvenience. of 1954, as amended, and Title 10 of the information, analyze relevant issues and Code of Federal Regulations (10 CFR) facts, and formulate proposed positions If attending this meeting, please enter Part 50, ‘‘Domestic Licensing of and actions, as appropriate, for through the One White Flint North Production and Utilization Facilities,’’ deliberation by the Full Committee. building, 11555 Rockville Pike, and Part 52, ‘‘Licenses, Certifications, Members of the public desiring to Rockville, MD. After registering with and Approvals for Nuclear Power provide oral statements and/or written security, please contact Mr. Theron Plants.’’ comments should notify the Designated Brown (240–888–9835) to be escorted to Federal Official (DFO), Antonio Dias the meeting room. 1 CP holders, as used in this Order, includes CPs, (Telephone 301–415–6805 or Email: in active or deferred status, as identified in [email protected]) five days prior to Attachment 1 to this Order (i.e., Watts Bar, Unit 2; the meeting, if possible, so that and Bellefonte, Units 1 and 2)

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II temperature reaction of steam and United States. Therefore, continued On March 11, 2011, a magnitude 9.0 zirconium fuel cladding generating operation and continued licensing earthquake struck off the coast of the hydrogen gas. This concern persisted activities do not pose an imminent Japanese island of Honshu. The primarily due to a lack of readily threat to public health and safety. earthquake resulted in a large tsunami, available and reliable information on However, the NRC’s assessment of new estimated to have exceeded 14 meters water levels in the spent fuel pools. insights from the events at Fukushima (45 feet) in height, that inundated the Helicopter water drops, water cannons, Dai-ichi leads the NRC staff to conclude Fukushima Dai-ichi and cement delivery vehicles with that additional requirements must be site. articulating booms were used to refill imposed on Licensees and CP holders to The earthquake and tsunami the pools, which diverted resources and increase the capability of nuclear power produced widespread devastation across attention from other efforts. Subsequent plants to mitigate beyond-design-basis northeastern Japan and significantly analysis determined that the water level external events. These additional affected the infrastructure and industry in the Unit 4 spent fuel pool did not requirements represent a substantial drop below the top of the stored fuel increase in the protection of public in the northeastern coastal areas of and no significant fuel damage health and safety. The Commission has Japan. When the earthquake occurred, occurred. The lack of information on the decided to administratively exempt this Fukushima Dai-ichi Units 1, 2, and 3 condition of the spent fuel pools Order from applicable provisions of the contributed to a poor understanding of Backfit Rule, 10 CFR 50.109, and the were in operation and Units 4, 5, and 6 possible radiation releases and issue finality requirements in 10 CFR were shut down for routine refueling adversely impacted effective 52.63 and 10 CFR Part 52, Appendix D, and maintenance activities. The Unit 4 prioritization of emergency response Paragraph VIII. reactor fuel was offloaded to the Unit 4 actions by decision makers. Additional details on an acceptable spent fuel pool. Following the Following the events at the approach for complying with this Order earthquake, the three operating units Fukushima Dai-ichi nuclear power will be contained in final interim staff automatically shut down and offsite plant, the NRC established a senior-level guidance (ISG) scheduled to be issued power was lost to the entire facility. The agency task force referred to as the Near- by the NRC in August 2012. This emergency diesel generators (EDGs) Term Task Force (NTTF). The NTTF guidance will include a template to be started at all six units providing was tasked with conducting a used for the plan that will be submitted alternating current (ac) electrical power systematic and methodical review of the in accordance with Section IV, to critical systems at each unit. The NRC regulations and processes and Condition C.1 below. facility response to the earthquake determining if the agency should make III appears to have been normal. additional improvements to these Approximately 40 minutes following programs in light of the events at Reasonable assurance of adequate the earthquake and shutdown of the Fukushima Dai-ichi. As a result of this protection of public health and safety operating units, the first large tsunami review, the NTTF developed a and assurance of the common defense wave inundated the site, followed by comprehensive set of recommendations, and security are the fundamental NRC additional waves. The tsunami caused documented in SECY–11–0093, ‘‘Near- regulatory objectives. Compliance with extensive damage to site facilities and Term Report and Recommendations for NRC requirements plays a critical role resulted in a complete loss of all ac Agency Actions Following the Events in in giving the NRC confidence that electrical power at Units 1 through 5, a Japan,’’ dated July 12, 2011. These Licensees and CP holders are condition known as station blackout. In recommendations were modified by the maintaining an adequate level of public addition, all direct current electrical NRC staff following interactions with health and safety and common defense power was lost early in the event on stakeholders. Documentation of the NRC and security. While compliance with Units 1 and 2 and after some period of staff’s efforts is contained in SECY–11– NRC requirements presumptively time at the other units. Unit 6 retained 0124, ‘‘Recommended Actions To Be ensures adequate protection, new the function of one air-cooled EDG. Taken Without Delay From the Near- information may reveal that additional Despite their actions, the operators lost Term Task Force Report,’’ dated requirements are warranted. In such the ability to cool the fuel in the Unit September 9, 2011, and SECY–11–0137, situations, the Commission may act in 1 reactor after several hours, in the Unit ‘‘Prioritization of Recommended accordance with its statutory authority 2 reactor after about 70 hours, and in the Actions To Be Taken in Response to under Section 161 of the Atomic Energy Unit 3 reactor after about 36 hours, Fukushima Lessons Learned,’’ dated Act of 1954, as amended, to require resulting in damage to the nuclear fuel October 3, 2011. Licensees and CP holders to take action shortly after the loss of cooling As directed by the Commission’s Staff in order to protect health and safety and capabilities. Requirements Memorandum (SRM) for common defense and security. The Unit 4 spent fuel pool contained SECY–11–0093, the NRC staff reviewed To protect public health and safety the highest heat load of the six units the NTTF recommendations within the from the inadvertent release of with the full core present in the spent context of the NRC’s existing regulatory radioactive materials, the NRC’s fuel pool and the refueling gates framework and considered the various defense-in-depth strategy includes installed. However, because Unit 4 had regulatory vehicles available to the NRC multiple layers of protection: (1) been shut down for more than 3 months, to implement the recommendations. Prevention of accidents by virtue of the the heat load was low relative to that SECY–11–0124 and SECY–11–0137 design, construction, and operation of present in spent fuel pools immediately established the NRC staff’s prioritization the plant; (2) mitigation features to following shutdown for reactor of the recommendations based upon the prevent radioactive releases should an refueling. Following the earthquake and potential safety enhancements. accident occur; and (3) emergency tsunami, the operators in the Units 3 Current regulatory requirements and preparedness programs that include and 4 control room focused their efforts existing plant capabilities allow the measures such as sheltering and on stabilizing the Unit 3 reactor. During NRC to conclude that a sequence of evacuation. The defense-in-depth the event, concern grew that the spent events such as the Fukushima Dai-ichi strategy also provides for multiple fuel was overheating, causing a high- accident is unlikely to occur in the physical barriers to contain the

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radioactive materials in the event of an personnel can effectively prioritize implementation of the spent fuel accident. The barriers are the fuel emergency actions. monitoring requirements is warranted at cladding, the reactor coolant pressure The Commission has determined that this time. In addition, pursuant to 10 boundary, and the containment. These the spent fuel pool instrumentation CFR 2.202, the NRC finds that the defense-in-depth features are embodied required by this Order represents a public health, safety, and interest in the existing regulatory requirements significant enhancement to the require that this Order be made and thereby provide adequate protection protection of public health and safety immediately effective. of public health and safety. and is an appropriate response to the Based upon the considerations set In the case of spent fuel pools, insights from the Fukushima Dai-ichi forth above, the Commission has compliance with existing regulations accident. While this consideration is determined that all power reactor and guidance presumptively provides qualitative in nature, the Commission licensees and CP holders must have a reasonable assurance of the safe storage has long taken the position that the reliable means of remotely monitoring of spent fuel. In particular, Appendix A, determination as to whether proposed wide-range spent fuel pool levels to ‘‘General Design Criteria for Nuclear backfits represent a substantial safety support effective prioritization of event improvement may be qualitative in Power Plants,’’ to 10 CFR part 50 mitigation and recovery actions in the nature. Staff Requirements establishes the general design criteria event of a beyond-design-basis external Memorandum, SECY–93–086, ‘‘Backfit (GDC) for nuclear power plants. All event. These new requirements provide Considerations’’ (June 30, 1993), pp. 1– currently operating reactors were a greater capability, consistent with the 2. However the Commission does not, at licensed to the GDC or meet the intent overall defense-in-depth philosophy, this time, have sufficient information to of the GDC. The GDC provide the design and therefore greater assurance of complete a full backfit analysis of the features of the spent fuel storage and protection of public health and safety spent fuel pool instrumentation that handling systems and the protection of from the challenges posed by beyond- would be required by this Order. The these systems from natural phenomena design-basis external events to power NRC is analyzing the insights gained reactors. Accordingly, the Commission and operational events. The accidents from the Fukushima Dai-ichi accident considered during licensing of U.S. concludes that all operating reactor on an accelerated timeline. licensees and CPs under Part 50 nuclear power plants typically include Additionally, the NRC has considered failure of the forced cooling system and identified in Attachment 1 to this Order the Congressional intent that the agency shall be modified to include the loss of spent fuel pool inventory at a act expeditiously on Tier 1 specified rate within the capacity of the requirements identified in Attachment 2 recommendations. to this Order. All combined licenses makeup water system. Further, spent The Commission has recognized, in fuel pools at U.S. nuclear power plants (COLs) under Part 52 identified in exceptional circumstances, that some Attachment 1 to this Order shall be rely on maintenance of an adequate proposed rules may not meet the inventory of water under accident modified to include the requirements requirements specified in the Backfit identified in Attachment 3 to this Order. conditions to provide containment, as Rule but nevertheless should be adopted well as the cooling and shielding safety by the NRC. Hence, the Commission IV functions. advised the NRC staff that it would Accordingly, pursuant to Sections During the events in Fukushima, consider, on a case-by-case basis, 161b, 161i, 161o, and 182 of the Atomic responders were without reliable whether a proposed regulatory action Energy Act of 1954, as amended, and instrumentation to determine water should be adopted as an ‘‘exception’’ to the Commission’s regulations in 10 CFR level in the spent fuel pool. This caused the Backfit Rule. This Order represents 2.202, and 10 CFR parts 50 and 52, it is concerns that the pool may have boiled such a case. Therefore, the Commission hereby ordered, effective immediately, dry, resulting in fuel damage.2 has decided to administratively exempt that all licenses and construction Fukushima demonstrated the confusion this Order from the Backfit Rule and the permits identified in attachment 1 to and misapplication of resources that can issue finality requirements in 10 CFR this order are modified as follows: result from beyond-design-basis external 52.63 and 10 CFR part 52, Appendix D, events when adequate instrumentation paragraph VIII for several reasons. A.1. All holders of CPs issued under Part The Fukushima Dai-ichi accident was 50 shall, notwithstanding the provisions of is not available. any Commission regulation or CP to the The spent fuel pool level unprecedented in terms of initiating contrary, comply with the requirements instrumentation at U.S. nuclear power cause and the particular failure described in Attachment 2 to this Order plants is typically narrow range and, sequence. In addition, our review of this except to the extent that a more stringent therefore, only capable of monitoring event has highlighted the benefits that requirement is set forth in the CP. These CP can be derived from the availability of holders shall complete full implementation normal and slightly off-normal prior to issuance of an operating license. conditions. Although the likelihood of a more diverse instrumentation. Consistent with the final Aircraft Impact 2. All holders of operating licenses issued catastrophic event affecting nuclear Assessment Rule, 10 CFR 50.150, 74 FR under Part 50 shall, notwithstanding the power plants and the associated spent provisions of any Commission regulation or 28112 (June 12, 2009), the Commission’s fuel pools in the United States remains license to the contrary, comply with the decision to administratively exempt this very low, beyond-design-basis external requirements described in Attachment 2 to Order from compliance with the Backfit events could challenge the ability of this Order except to the extent that a more Rule is a highly exceptional action existing instrumentation to provide stringent requirement is set forth in the limited to the insights associated with license. These Licensees shall promptly start emergency responders with reliable the extraordinary underlying implementation of the requirements in information on the condition of spent circumstances of the Fukushima Dai- Attachment 2 to the Order and shall fuel pools. Reliable and available ichi accident and the NRC’s lessons complete full implementation no later than indication is essential to ensure plant learned. Furthermore, the extensive two (2) refueling cycles after submittal of the overall integrated plan, as required in stakeholder engagement and broad 2 See Institute of Nuclear Power Operations Condition C.1.a, or December 31, 2016, (INPO) 11–005, ‘‘Special Report on the Nuclear endorsement for timely action support whichever comes first. Accident at the Fukushima Daiichi Nuclear Power the Commission’s judgment that 3. All holders of COLs issued under Part Station,’’ Revision 0, issued November 2011, p. 36. immediate action to commence 52 shall, notwithstanding the provisions of

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any Commission regulation or license to the with 10 CFR 50.4 and 10 CFR 52.3, as unless they seek an exemption in contrary, comply with the requirements applicable. accordance with the procedures described in Attachment 3 to this Order As applicable, the Director, Office of described below. except to the extent that a more stringent Nuclear Reactor Regulation or the To comply with the procedural requirement is set forth in the license. These Director, Office of New Reactors may, in requirements of E-Filing, at least 10 Licensees shall promptly start implementation of the requirements in writing, relax or rescind any of the days prior to the filing deadline, the Attachment 3 to the Order and shall above conditions upon demonstration participant should contact the Office of complete full implementation prior to initial by the Licensee or CP holder of good the Secretary by email at fuel load. cause. [email protected], or by telephone at (301) 415–1677, to request (1) a B.1. All Licensees and CP holders shall, V within twenty (20) days of the date of this digital ID certificate, which allows the Order, notify the Commission (1) if they are In accordance with 10 CFR 2.202, the participant (or its counsel or unable to comply with any of the Licensee or CP holder must, and any representative) to digitally sign requirements described in Attachment 2 or other person adversely affected by this documents and access the E-Submittal Attachment 3, (2) if compliance with any of Order may, submit an answer to this server for any proceeding in which it is the requirements is unnecessary in their Order, and may request a hearing on participating; and (2) advise the specific circumstances, or (3) if this Order, within twenty (20) days of implementation of any of the requirements Secretary that the participant will be would cause the Licensee or CP holder to be the date of this Order. Where good cause submitting a request or petition for in violation of the provisions of any is shown, consideration will be given to hearing (even in instances in which the Commission regulation or the facility license. extending the time to answer or to participant, or its counsel or The notification shall provide the Licensee’s request a hearing. A request for representative, already holds an NRC- or CP holder’s justification for seeking relief extension of time in which to submit an issued digital ID certificate). Based upon from or variation of any specific requirement. answer or request a hearing must be this information, the Secretary will 2. Any Licensee or CP holder that made in writing to the Director, Office establish an electronic docket for the considers that implementation of any of the of Nuclear Reactor Regulation or to the hearing in this proceeding if the requirements described in Attachment 2 or Director, Office of New Reactors, U.S. Secretary has not already established an Attachment 3 to this Order would adversely Nuclear Regulatory Commission, impact safe and secure operation of the electronic docket. facility must notify the Commission, within Washington, DC 20555, and include a Information about applying for a twenty (20) days of this Order, of the adverse statement of good cause for the digital ID certificate is available on impact, the basis for its determination that extension. The answer may consent to NRC’s public Web site at http:// the requirement has an adverse impact, and this Order. www.nrc.gov/site-help/e-submittals/ either a proposal for achieving the same If a hearing is requested by a Licensee, apply-certificates.html. System objectives specified in the Attachment 2 or CP holder, or a person whose interest is requirements for accessing the Attachment 3 requirement in question, or a adversely affected, the Commission will E-Submittal server are detailed in NRC’s schedule for modifying the facility to address issue an Order designating the time and ‘‘Guidance for Electronic Submission,’’ the adverse condition. If neither approach is place of any hearings. If a hearing is which is available on the agency’s appropriate, the Licensee or CP holder must held, the issue to be considered at such public Web site at http://www.nrc.gov/ supplement its response to Condition B.1 of hearing shall be whether this Order this Order to identify the condition as a site-help/e-submittals.html. Participants requirement with which it cannot comply, should be sustained. Pursuant to 10 CFR may attempt to use other software not with attendant justifications as required in 2.202(c)(2)(i), the Licensee, CP holder, listed on the Web site, but should note Condition B.1. or any other person adversely affected that the NRC’s E-Filing system does not C.1.a. All holders of operating licenses by this Order, may, in addition to support unlisted software, and the NRC issued under Part 50 shall by February 28, demanding a hearing, at the time the Meta System Help Desk will not be able 2013, submit to the Commission for review answer is filed or sooner, move the to offer assistance in using unlisted an overall integrated plan, including a presiding officer to set aside the software. description of how compliance with the immediate effectiveness of the Order on If a participant is electronically requirements described in Attachment 2 will the ground that the Order, including the submitting a document to the NRC in be achieved. b. All holders of CPs issued under Part 50 need for immediate effectiveness, is not accordance with the E-Filing rule, the or COLs issued under Part 52 shall, within based on adequate evidence but on mere participant must file the document one (1) year after issuance of the final ISG, suspicion, unfounded allegations, or using the NRC’s online, Web-based submit to the Commission for review an error. submission form. In order to serve overall integrated plan, including a All documents filed in NRC documents through the Electronic description of how compliance with the adjudicatory proceedings, including a Information Exchange, users will be requirements described in Attachment 2 or request for hearing, a petition for leave required to install a Web browser plug- Attachment 3 will be achieved. to intervene, any motion or other in from the NRC Web site. Further 2. All Licensees and CP holders shall document filed in the proceeding prior information on the Web-based provide an initial status report sixty (60) days to the submission of a request for after the issuance of the final ISG, and at six submission form, including the (6)-month intervals following submittal of the hearing or petition to intervene, and installation of the Web browser plug-in, overall integrated plan, as required in documents filed by interested is available on the NRC’s public Web Condition C.1, which delineates progress governmental entities participating site at http://www.nrc.gov/site-help/e- made in implementing the requirements of under 10 CFR 2.315(c), must be filed in submittals.html. this Order. accordance with the NRC E-Filing rule Once a participant has obtained a 3. All Licensees and CP holders shall (72 FR 49139, August 28, 2007). The digital ID certificate and a docket has report to the Commission when full E-Filing process requires participants to been created, the participant can then compliance with the requirements described submit and serve all adjudicatory submit a request for hearing or petition in Attachment 2 or Attachment 3 is achieved. documents over the internet, or in some for leave to intervene. Submissions Licensee or CP holder responses to cases to mail copies on electronic should be in Portable Document Format Conditions B.1, B.2, C.1, C.2, and C.3, storage media. Participants may not (PDF) in accordance with NRC guidance above, shall be submitted in accordance submit paper copies of their filings available on the NRC public Web site at

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http://www.nrc.gov/site-help/e- depositing the document with the Mr. Christopher J. Schwarz, Vice submittals.html. A filing is considered provider of the service. A presiding President, Operations, Entergy complete at the time the documents are officer, having granted an exemption Operations, Inc., Arkansas Nuclear submitted through the NRC’s E-Filing request from using E-Filing, may require One, 1448 S.R. 333, Russellville, AR system. To be timely, an electronic a participant or party to use 72802 filing must be submitted to the E-Filing E-Filing if the presiding officer Beaver Valley system no later than 11:59 p.m. Eastern subsequently determines that the reason Time on the due date. Upon receipt of for granting the exemption from use of First Energy Nuclear Operating Co., a transmission, the E-Filing system E-Filing no longer exists. Docket Nos. 50–334 and 50–412, time-stamps the document and sends Documents submitted in adjudicatory License Nos. DPR–66 and NPF–73 the submitter an email notice proceedings will appear in NRC’s Mr. Paul A. Harden, Site Vice President, confirming receipt of the document. The electronic hearing docket, which is FirstEnergy Nuclear Operating E-Filing system also distributes an email available to the public at http:// Company, Mail Stop A–BV–SEB1, notice that provides access to the ehd1.nrc.gov/ehd/, unless excluded P.O. Box 4, Route 168, Shippingport, document to the NRC Office of the pursuant to an order of the Commission, PA 15077 General Counsel and any others who or the presiding officer. Participants are Bellefonte Nuclear Power Station have advised the Office of the Secretary requested not to include personal Tennessee Valley Authority, Docket that they wish to participate in the privacy information, such as social Nos. 50–438 and 50–439, proceeding, so that the filer need not security numbers, home addresses, or Construction Permit Nos. CPPR No. serve the documents on those home phone numbers in their filings, 122 and CPPR No. 123 participants separately. Therefore, unless an NRC regulation or other law applicants and other participants (or Mr. Michael D. Skaggs, Senior Vice requires submission of such President, Nuclear Generation their counsel or representative) must information. With respect to apply for and receive a digital ID Development and Construction, copyrighted works, except for limited Tennessee Valley Authority, 6A certificate before a hearing request/ excerpts that serve the purpose of the petition to intervene is filed so that they Lookout Place, 1101 Market Street, adjudicatory filings and would Chattanooga, TN 37402–2801 can obtain access to the document via constitute a Fair Use application, the E-Filing system. participants are requested not to include Braidwood Station A person filing electronically using copyrighted materials in their the agency’s adjudicatory E-Filing Exelon Generation Co., LLC, Docket submission. Nos. STN 50–456 and STN 50–457, system may seek assistance by If a person other than the Licensee or contacting the NRC Meta System Help License Nos. NPF–72 and NPF–77 CP holder requests a hearing, that Mr. Michael J. Pacilio, President and Desk through the ‘‘Contact Us’’ link person shall set forth with particularity located on the NRC Web site at http:// Chief Nuclear Officer, Exelon Nuclear, the manner in which his interest is www.nrc.gov/site-help/e- 4300 Winfield Road, Warrenville, IL adversely affected by this Order and submittals.html, by email at 60555 shall address the criteria set forth in 10 [email protected], or by a toll- CFR 2.309(d). Browns Ferry Nuclear Plant free call at (866) 672–7640. The NRC In the absence of any request for Tennessee Valley Authority, Docket Meta System Help Desk is available hearing, or written approval of an Nos. 50–259, 50–260 and 50–296, between 8 a.m. and 8 p.m., Eastern extension of time in which to request a License Nos. DPR–33, DPR–52 and Time, Monday through Friday, hearing, the provisions specified in DPR–68 excluding government holidays. Mr. Preston D. Swafford, Chief Nuclear Participants who believe that they Section IV above shall be final twenty Officer and Executive Vice President, have a good cause for not submitting (20) days from the date of this Order Tennessee Valley Authority, 3R documents electronically must file an without further order or proceedings. If Lookout Place, 1101 Market Street, exemption request, in accordance with an extension of time for requesting a Chattanooga, TN 37402–2801 10 CFR 2.302(g), with their initial paper hearing has been approved, the filing requesting authorization to provisions specified in Section IV shall Brunswick Steam Electric Plant be final when the extension expires if a continue to submit documents in paper Carolina Power & Light Co., Docket Nos. format. Such filings must be submitted hearing request has not been received. An answer or a request for hearing shall 50–325 and 50–324, License Nos. by: (1) First class mail addressed to the DPR–71 and DPR–62 Office of the Secretary of the not stay the immediate effectiveness of this order. Mr. Michael J. Annacone, Vice Commission, U.S. Nuclear Regulatory President, Carolina Power & Light Commission, Washington, DC 20555– For the Nuclear Regulatory Commission. Company, Brunswick Steam Electric 0001, Attention: Rulemaking and Dated this 12th day of March 2012. Plant, P. O. Box 10429, Southport, NC Adjudications Staff; or (2) courier, Eric J. Leeds, 28461 express mail, or expedited delivery Director, Office of Nuclear Reactor Byron Station service to the Office of the Secretary, Regulation. Sixteenth Floor, One White Flint North, Michael R. Johnson, Exelon Generation Co., LLC, Docket 11555 Rockville Pike, Rockville, Director, Office of New Reactors. Nos. STN 50–454 and STN 50–455, Maryland, 20852, Attention: License Nos. NPF–37 and NPF–66 Rulemaking and Adjudications Staff. Power Reactor Licensees and Licensees Mr. Michael J. Pacilio, President and Participants filing a document in this With Active and/or Deferred Chief Nuclear Officer, Exelon Nuclear, manner are responsible for serving the Construction Permits 4300 Winfield Road, Warrenville, IL document on all other participants. 60555 Filing is considered complete by first- class mail as of the time of deposit in Entergy Operations, Inc., Docket Nos. Callaway Plant the mail, or by courier, express mail, or 50–313 and 50–368 License Nos. Union Electric Co., Docket No. 50–483, expedited delivery service upon DPR–51 and NPF–6 License No. NPF–30

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Mr. Adam C. Heflin, Senior Vice Davis-Besse Nuclear Power Station Fort Calhoun Station President and Chief Nuclear Officer, First Energy Nuclear Operating Co., Omaha Public Power District, Docket Union Electric Company, P. O. Box Docket No. 50–346, License No. NPF– No. 50–285, License No. DPR–40 620, Fulton, MO 65251 3 Mr. David J. Bannister, Vice President Calvert Cliffs Nuclear Power Plant Mr. Barry S. Allen, Site Vice President, and Chief Nuclear Officer, Omaha FirstEnergy Nuclear Operating Public Power District, 444 South 16th Calvert Cliffs Nuclear Power Plant, LLC, St. Mall, Omaha, NE 68102–2247 Docket Nos. 50–317 and 50–318, Company, c/o Davis-Besse NPS, 5501 License Nos. DPR–53 and DPR–69 N. State Route 2, Oak Harbor, OH Grand Gulf Nuclear Station Mr. George H. Gellrich, Vice President, 43449–9760 Entergy Operations, Inc., Docket No. 50– Calvert Cliffs Nuclear Power Plant, Diablo Canyon Power Plant 416, License No. NPF–29 LLC, Calvert Cliffs Nuclear Power Mr. Michael Perito, Vice President, Plant, 1650 Calvert Cliffs Parkway, Pacific Gas & Electric Co., Docket Nos. Operations, Entergy Operations, Inc., Lusby, MD 20657–4702 50–275 and 50–323, License Nos. Grand Gulf Nuclear Station, Unit 1, DPR–80 and DPR–82 7003 Bald Hill Road, Port Gibson, MS Mr. John T. Conway, Senior Vice 39150 President—Energy Supply and Chief Duke Energy Carolinas, LLC, Docket H.B. Robinson Steam Electric Plant Nos. 50–413 and 50–414, License Nos. Nuclear Officer, Pacific Gas and NPF–35 and NPF–52 Electric Company, Diablo Canyon Carolina Power & Light Co., Docket No. Mr. James R. Morris, Site Vice President, Power Plant, 77 Beale Street, Mail 50–261, License No. DPR–23 Mr. Robert J. Duncan II, Vice President, Duke Energy Carolinas, LLC, Catawba Code B32, San Francisco, CA 94105 Carolina Power & Light Company, Nuclear Station, 4800 Concord Road, Donald C. Cook Nuclear Plant 3581 West Entrance Road, Hartsville, York, SC 29745 Indiana Michigan Power Co., Docket SC 29550 Nos. 50–315 and 50–316, License Nos. Hope Creek Generating Station DPR–58 and DPR–74 Exelon Generation Co., LLC, Docket No. PSEG Nuclear, LLC, Docket No. 50–354, 50–461, License No. NPF–62 Mr. Lawrence J. Weber, Senior Vice President and Chief Nuclear Officer, License No. NPF–57 Mr. Michael J. Pacilio, President and Mr. Thomas Joyce, President and Chief Indiana Michigan Power Company, Chief Nuclear Officer, Exelon Nuclear, Nuclear Officer, PSEG Nuclear LLC— Nuclear Generation Group, One Cook 4300 Winfield Road, Warrenville, IL N09, P. O. Box 236, Hancocks Bridge, Place, Bridgman, MI 49106 60555 NJ 08038 Dresden Nuclear Power Station Columbia Generating Station Indian Point Energy Center , Docket No. 50–397, Exelon Generation Co., LLC, Docket Entergy Nuclear Operations, Inc., License No. NPF–21 Nos. 50–237 and 50–249, License Nos. Docket Nos. 50–247 and 50–286, Mr. Mark E. Reddemann, Chief DPR–19 and DPR–25 License Nos. DPR–26 and DPR–64 Executive Officer, Energy Northwest, Mr. Michael J. Pacilio, President and Mr. John Ventosa, Vice President, MD 1023, P.O. Box 968, Richland, Chief Nuclear Officer, Exelon Nuclear, Operations, Entergy Nuclear WA 99352 4300 Winfield Road, Warrenville, IL Operations, Inc., Indian Point Energy 60555 Center, 450 Broadway, GSB, P.O. Box Comanche Peak Nuclear Power Plant Duane Arnold Energy Center 249, Buchanan, NY 10511–0249 Luminant Generation Co., LLC, Docket NextEra Energy Duane Arnold, LLC, James A. FitzPatrick Nuclear Power Nos. 50–445 and 50–446, License Nos. Plant NPF–87 and NPF–89 Docket No. 50–331, License No. DPR– Mr. Rafael Flores, Senior Vice President 49 Entergy Nuclear Operations, Inc., and Chief Nuclear Officer, Luminant Mr. Peter Wells, Site Vice President, Docket No. 50–333, License No. DPR– Generation Company, LLC, Attn: NextEra Energy, Duane Arnold Energy 59 Regulatory Affairs, P. O. Box 1002, Center, 3277 DAEC Road, Palo, IA Mike Colomb, Vice President, Glen Rose, TX 76043 52324–9785 Operations, Entergy Nuclear Operations, Inc., James A. FitzPatrick Edwin I. Hatch Nuclear Plant Nuclear Power Plant, P.O. Box 110, Nebraska Public Power District, Docket Southern Nuclear Operating Co., Docket Lycoming, NY 13093 No. 50–298, License No. DPR–46 Nos. 50–321 and 50–366, License Nos. Joseph M. Farley Nuclear Plant DPR–57 and NPF–5 Mr. Brian J. O’Grady, Vice President— Southern Nuclear Operating Co., Docket Mr. Dennis R. Madison, Vice President, Nuclear and Chief Nuclear Officer, Nos. 50–348 and 50–364, License Nos. Southern Nuclear Operating Nebraska Public Power District, 72676 NPF–2 and NPF–8 648A Avenue, P.O. Box 98, Company, Inc., Edwin I. Hatch Mr. Tom Lynch, Vice President—Farley, Brownville, NE 68321 Nuclear Plant, 11028 Hatch Parkway Southern Nuclear Operating North, Baxley, GA 31513 Crystal River Nuclear Generating Plant Company, Inc., Joseph M. Farley Fermi Nuclear Plant, 7388 North State Florida Power Corp., Docket No. 50– Highway 95, Columbia, AL 36319 302, License No. DPR–72 Detroit Edison Co., Docket No. 50–341, Mr. Jon A. Franke, Vice President, Attn: License No. NPF–43 Kewaunee Power Station Supervisor, Licensing & Regulatory Mr. Jack M. Davis, Senior Vice President Dominion Energy Kewaunee, Inc., Affairs, Progress Energy, Inc., Crystal and Chief Nuclear Officer, Detroit Docket No. 50–305, License No. DPR– River Nuclear Plant (NA2C), 15760 Edison Company, Fermi 2—210 NOC, 43 West Power Line Street, Crystal River, 6400 North Dixie Highway, Newport, Mr. David A. Heacock, President and FL 34428–6708 MI 48166 Chief Nuclear Officer, Dominion

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Energy Kewaunee, Inc., Innsbrook Mr. Preston Gillespie, Site Vice Mr. Larry Meyer, Site Vice President, Technical Center, 5000 Dominion President, , NextEra Energy Point Beach, LLC, Boulevard, Glen Allen, VA 23060– Duke Energy Carolinas, LLC, 7800 Point Beach Nuclear Plant, Units 1 & 6711 Rochester Highway, Seneca, SC 29672 2, 6610 Nuclear Road, Two Rivers, WI 54241–9516 LaSalle County Station Oyster Creek Nuclear Generating Station Exelon Generation Co., LLC, Docket Exelon Generation Co., LLC, Docket No. Prairie Island Nuclear Generating Plant Nos. 50–373 and 50–374, License Nos. 50–219, License No. DPR–16 Northern States Power Co. Minnesota, NPF–11 and NPF–18 Mr. Michael J. Pacilio, President and Docket Nos. 50–282 and 50–306, Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon Nuclear, License Nos. DPR–42 and DPR–60 Chief Nuclear Officer, Exelon Nuclear, 4300 Winfield Road, Warrenville, IL Mr. Mark A. Schimmel, Site Vice 4300 Winfield Road, Warrenville, IL 60555 President, Northern States Power 60555 Company—Minnesota, Prairie Island Palisades Nuclear Plant Nuclear Generating Plant, 1717 Limerick Generating Station Entergy Nuclear Operations, Inc., Wakonade Drive East, Welch, MN Exelon Generation Co., LLC, Docket Docket No. 50–255, License No. DPR– 55089–9642 Nos. 50–352 and 50–353, License Nos. 20 NPF–39 and NPF–85 Mr. Anthony J. Vitale, Site Vice Quad Cities Nuclear Power Station Mr. Michael J. Pacilio, President and President—Palisades, Entergy Nuclear Exelon Generation Co., LLC, Docket Chief Nuclear Officer, Exelon Nuclear, Operations, Inc., Palisades Nuclear Nos. 50–254 and 50–265, License Nos. 4300 Winfield Road, Warrenville, IL Plant, 27780 Blue Star Memorial DPR–29 and DPR–30 60555 Highway, Covert, MI 49043 Mr. Michael J. Pacilio, President and Chief Nuclear Officer, Exelon Nuclear, Millstone Nuclear Power Station Palo Verde Nuclear Generating Station 4300 Winfield Road, Warrenville, IL Dominion Nuclear Connecticut, Inc., Arizona Public Service Company, 60555 Docket Nos. 50–336 and 50–423, Docket Nos. STN 50–528, STN 50–529 License Nos. DPR–65 and NPF–49 and STN 50–530, License Nos. NPF– R.E. Ginna Nuclear Power Plant Mr. David A. Heacock, President and 41, NPF–51 and NPF–74 R.E. Ginna Nuclear Power Plant, LLC, Chief Nuclear Officer, Dominion Mr. Randall K. Edington, Executive Vice Docket No. 50–244, License No. DPR– Nuclear Connecticut, Inc., Innsbrook President Nuclear and Chief Nuclear 18 Technical Center, 5000 Dominion Officer, Arizona Public Service Co., Mr. Joseph E. Pacher, Vice President, Boulevard, Glen Allen, VA 23060– P.O. Box 52034, MS 7602, Phoenix, R.E. Ginna Nuclear Power Plant, LLC, 6711 AZ 85072–2034 R.E. Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519 Monticello Nuclear Generating Plant Peach Bottom Atomic Power Station Northern States Power Company, Exelon Generation Co., LLC, Docket River Bend Station Docket No. 50–263, License No. DPR– Nos. 50–277 and 50–278, License Nos. Entergy Operations, Inc., Docket No. 50– 22 DPR–44 and DPR–56 458, License No. NPF–47 Mr. Timothy J. O’Connor, Site Vice Mr. Michael J. Pacilio, President and Mr. Eric W. Olson, Vice President, President, Northern States Power Chief Nuclear Officer, Exelon Nuclear, Operations, Entergy Operations, Inc., Company—Minnesota, Monticello 4300 Winfield Road, Warrenville, IL River Bend Station, 5485 U.S. Nuclear Generating Plant, 2807 West 60555 Highway 61N, St. Francisville, LA County Road 75, Monticello, MN 70775 Perry Nuclear Power Plant 55362–9637 First Energy Nuclear Operating Co., Salem Nuclear Generating Station Nine Mile Point Nuclear Station Docket No. 50–440, License No. NPF– PSEG Nuclear, LLC, Docket Nos. 50–272 Nine Mile Point Nuclear Station, LLC, 58 and 50–311, License Nos. DPR–70 and Docket Nos. 50–220 and 50–410, Mr. Vito A. Kaminskas, Site Vice DPR–75 License Nos. DPR–63 and NPF–69 President—Nuclear—Perry, Mr. Thomas Joyce, President and Chief Mr. Ken Langdon, Vice President Nine FirstEnergy Nuclear Operating Nuclear Officer, PSEG Nuclear LLC— Mile Point, Nine Mile Point Nuclear Company, Perry Nuclear Power Plant, N09, P.O. Box 236, Hancocks Bridge, Station, LLC, P.O. Box 63, Lycoming, 10 Center Road, A290, Perry, OH NJ 08038 NY 13093 44081 San Onofre Nuclear Generating Station North Anna Power Station Pilgrim Nuclear Power Station Unit No. Southern California Edison Co., Docket Virginia Electric & Power Co., Docket 1 Nos. 50–361 and 50–362, License Nos. Nos. 50–338 and 50–339, License Nos. Entergy Nuclear Operations, Inc., NPF–10 and NPF–15 NPF–4 and NPF–7 Docket No. 50–293, License No. DPR– Mr. Peter T. Dietrich, Senior Vice Mr. David A. Heacock, President and 35 President and Chief Nuclear Officer, Chief Nuclear Officer, Dominion Mr. Robert Smith, Vice President and Southern California Edison Company, Nuclear, Innsbrook Technical Center, Site Vice President, Entergy Nuclear San Onofre Nuclear Generating 5000 Dominion Boulevard, Glen Operations, Inc., Pilgrim Nuclear Station, P.O. Box 128, San Clemente, Allen, VA 23060–6711 Power Station, 600 Rocky Hill Road, CA 92674–0128 Plymouth, MA 02360–5508 Oconee Nuclear Station Seabrook Duke Energy Carolinas, LLC, Docket Point Beach Nuclear Plant NextEra Energy Seabrook, LLC, Docket Nos. 50–269, 50–270 and 50–287, NextEra Energy Point Beach, LLC, No. 50–443, License No. NPF–86 License Nos. DPR–38, DPR–47 and Docket Nos. 50–266 and 50–301, Mr. Paul Freeman, Site Vice President, DPR–55 License Nos. DPR–24 and DPR–27 NextEra Energy Seabrook, LLC, c/o

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Mr. Michael O’Keefe, NextEra Energy Mr. Michael J. Pacilio, President and Mr. Preston D. Swafford, Chief Nuclear Seabrook, LLC, P.O. Box 300, Chief Nuclear Officer, Exelon Nuclear, Officer and Executive Vice President, Seabrook, NH 03874 4300 Winfield Road, Warrenville, IL Tennessee Valley Authority, 3R 60555 Lookout Place, 1101 Market Street, Chattanooga, TN 37402–2801 Tennessee Valley Authority, Docket Turkey Point Nos. 50–327 and 50–328, License Nos. Florida Power & Light Co., Docket Nos. , Unit 2 DPR–77 and DPR–79 50–250 and 50–251, License Nos. Tennessee Valley Authority, Docket No. Mr. Preston D. Swafford, Chief Nuclear DPR–31 and DPR–41 50–391, Construction Permit No. Officer and Executive Vice President, Mr. Mano Nazar, Executive Vice CPPR No. 092 Tennessee Valley Authority, 3R President and Chief Nuclear Officer, Mr. Michael D. Skaggs, Senior Vice Lookout Place, 1101 Market Street, NextEra Energy, 700 Universe President, Nuclear Generation Chattanooga, TN 37402–2801 Boulevard, P.O. Box 14000, Juno Development and Construction, Beach, FL 33408–0420 Tennessee Valley Authority, 6A Shearon Harris Nuclear Power Plant Lookout Place, 1101 Market Street, Carolina Power & Light Co., Docket No. Vermont Yankee Nuclear Power Station Chattanooga, TN 37402–2801 50–400, License No. NPF–63 Entergy Nuclear Operations, Inc., William B. McGuire Nuclear Station Mr. Christopher L. Burton, Vice Docket No. 50–271, License No. DPR– President, Progress Energy Carolinas, 28 Duke Energy Carolinas, LLC, Docket Inc., Shearon Harris Nuclear Power Mr. Christopher J. Wamser, Site Vice Nos. 50–369 and 50–370, License Nos. Plant, P.O. Box 165, Mail Zone 1, New President, Entergy Nuclear NPF–9 and NPF–17 Hill, NC 27562–0165 Operations, Inc., Vermont Yankee Mr. Regis T. Repko, Vice President, Nuclear Power Station, 320 Governor Duke Energy Carolinas, LLC, McGuire South Texas Project Hunt Road, Vernon, VT 05354 Nuclear Site, 12700 Hagers Ferry STP Nuclear Operating Co., Docket Nos. Road, Huntersville, NC 28078 Virgil C. Summer Nuclear Station 50–498 and 50–499, License Nos. Wolf Creek Generating Station NPF–76 and NPF–80 South Carolina Electric & Gas Co., Mr. Edward D. Halpin, President, Chief Docket No. 50–395, License No. NPF– Wolf Creek Nuclear Operating Corp., Executive Officer and Chief Nuclear 12 Docket No. 50–482, License No. NPF– Officer, STP Nuclear Operating Mr. Thomas D. Gatlin, Vice President 42 Company, South Texas Project, P.O. Nuclear Operations, South Carolina Mr. Matthew W. Sunseri, President and Box 289, Wadsworth, TX 77483 Electric & Gas Company, Virgil C. Chief Executive Officer, Wolf Creek Summer Nuclear Station, Post Office Nuclear Operating Corporation, P.O. St. Lucie Plant Box 88, Mail Code 300, Jenkinsville, Box 411, Burlington, KS 66839 Florida Power & Light Co., Docket Nos. SC 29065 Requirements for Reliable Spent Fuel 50–335 and 50–389, License Nos. Vogtle Electric Generating Plant Pool Level Instrumentation at DPR–67 and NPF–16 Operating Reactor Sites and Mr. Mano Nazar, Executive Vice Southern Nuclear Operating Co., Docket Construction Permit Holders President and Chief Nuclear Officer, Nos. 50–424 and 50–425, License Nos. NextEra Energy, 700 Universe NPF–68 and NPF–81 All licensees identified in Attachment Boulevard, P.O. Box 14000, Juno Mr. Tom E. Tynan, Vice President, 1 to this Order shall have a reliable Beach, FL 33408–0420 Southern Nuclear Operating indication of the water level in Company, Inc., Vogtle Electric associated spent fuel storage pools Surry Power Station Generating Plant, 7821 River Road, capable of supporting identification of Virginia Electric & Power Co., Docket Waynesboro, GA 30830 the following pool water level Nos. 50–280 and 50–281, License Nos. conditions by trained personnel: (1) DPR–32 and DPR–37 Vogtle Electric Generating Plant, Units 3 Level that is adequate to support Mr. David A. Heacock, President and and 4 operation of the normal fuel pool Chief Nuclear Officer, Dominion Southern Nuclear Operating Co., Docket cooling system, (2) level that is adequate Nuclear, Innsbrook Technical Center, Nos. 52–025 and 52–026, License Nos. to provide substantial radiation 5000 Dominion Boulevard, Glen NPF–91 and NPF–92 shielding for a person standing on the Allen, VA 23060–6711 Mr. B.L. Ivey, Vice President, Regulatory spent fuel pool operating deck, and (3) Affairs, Southern Nuclear Operating level where fuel remains covered and Susquehanna Steam Electric Station Company, Inc., 40 Inverness Center actions to implement make-up water PPL Susquehanna, LLC, Docket Nos. Parkway, Bin B022, Birmingham, AL addition should no longer be deferred. 50–387 and 50–388, License Nos. 35242 1. The spent fuel pool level NPF–14 and NPF–22 instrumentation shall include the Mr. Timothy S. Rausch, Senior Vice Waterford Steam Electric Station following design features: President and Chief Nuclear Officer, Entergy Operations, Inc., Docket No. 50– 1.1 Instruments: The PPL Susquehanna, LLC, 769 Salem 382, License No. NPF–38 instrumentation shall consist of a Boulevard, NUCSB3, Berwick, PA Ms. Donna Jacobs, Vice President, permanent, fixed primary instrument 18603–0467 Operations, Entergy Operations, Inc., channel and a backup instrument Waterford Steam Electric Station, Unit channel. The backup instrument Three Mile Island Nuclear Station, Unit 3, 17265 River Road, Killona, LA channel may be fixed or portable. 1 70057–0751 Portable instruments shall have (* via corrected letter dated 3/13/12— capabilities that enhance the ability of ML12073A366), Exelon Generation Watts Bar Nuclear Plant, Unit 1 trained personnel to monitor spent fuel Co., LLC, Docket No. 50–289, License Tennessee Valley Authority, Docket No. pool water level under conditions that No. DPR–50 50–390, License No. NPF–90 restrict direct personnel access to the

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pool, such as partial structural damage, appropriate and accessible location. The • Electrical isolation and physical high radiation levels, or heat and display shall provide on-demand or separation between instrument channels humidity from a boiling pool. continuous indication of spent fuel pool • Display in the control room as part 1.2 Arrangement: The spent fuel water level. of the post-accident monitoring pool level instrument channels shall be 2. The spent fuel pool instrumentation • arranged in a manner that provides instrumentation shall be maintained Routine calibration and testing reasonable protection of the level available and reliable through As such, this Order requires Vogtle indication function against missiles that appropriate development and Units 3 and 4 to address the following may result from damage to the structure implementation of the following requirements that were not specified in over the spent fuel pool. This protection programs: the certified design. 1. The spent fuel pool level may be provided by locating the 2.1 Training: Personnel shall be instrumentation shall include the primary instrument channel and fixed trained in the use and the provision of following design features: portions of the backup instrument alternate power to the primary and channel, if applicable, to maintain 1.1 Arrangement: The spent fuel pool backup instrument channels. level instrument channels shall be instrument channel separation within 2.2 Procedures: Procedures shall be the spent fuel pool area, and to utilize arranged in a manner that provides established and maintained for the reasonable protection of the level inherent shielding from missiles testing, calibration, and use of the provided by existing recesses and indication function against missiles that primary and backup spent fuel pool may result from damage to the structure corners in the spent fuel pool structure. instrument channels. 1.3 Mounting: Installed instrument over the spent fuel pool. This protection 2.3 Testing and Calibration: channel equipment within the spent may be provided by locating the safety- Processes shall be established and fuel pool shall be mounted to retain its related instruments to maintain maintained for scheduling and design configuration during and instrument channel separation within implementing necessary testing and following the maximum seismic ground the spent fuel pool area, and to utilize calibration of the primary and backup motion considered in the design of the inherent shielding from missiles spent fuel pool level instrument spent fuel pool structure. provided by existing recesses and 1.4 Qualification: The primary and channels to maintain the instrument corners in the spent fuel pool structure. backup instrument channels shall be channels at the design accuracy. 1.2 Qualification: The level reliable at temperature, humidity, and Requirements for Reliable Spent Fuel instrument channels shall be reliable at radiation levels consistent with the Pool Level Instrumentation at temperature, humidity, and radiation spent fuel pool water at saturation Combined License Holder Reactor Sites levels consistent with the spent fuel conditions for an extended period. This pool water at saturation conditions for Attachment 2 to this Order for Part 50 reliability shall be established through an extended period. Licensees requires reliable indication of use of an augmented quality assurance 1.3 Power supplies: Instrumentation the water level in associated spent fuel process (e.g., a process similar to that channels shall provide for power storage pools capable of supporting connections from sources independent applied to the site fire protection identification of the following pool of the plant alternating current (ac) and program). 1.5 Independence: The primary water level conditions by trained direct current (dc) power distribution instrument channel shall be personnel: (1) level that is adequate to systems, such as portable generators or independent of the backup instrument support operation of the normal fuel replaceable batteries. Power supply channel. pool cooling system, (2) level that is designs should provide for quick and 1.6 Power supplies: Permanently adequate to provide substantial accessible connection of sources installed instrumentation channels shall radiation shielding for a person standing independent of the plant ac and dc each be powered by a separate power on the spent fuel pool operating deck, power distribution systems. Onsite supply. Permanently installed and and (3) level where fuel remains generators used as an alternate power portable instrumentation channels shall covered and actions to implement make- source and replaceable batteries used for provide for power connections from up water addition should no longer be instrument channel power shall have sources independent of the plant ac and deferred. sufficient capacity to maintain the level dc power distribution systems, such as The design bases of Vogtle Units 3 indication function until offsite resource portable generators or replaceable and 4 address many of these attributes availability is reasonably assured. batteries. Onsite generators used as an of spent fuel pool level instrumentation. 1.4 Accuracy: The instrument shall alternate power source and replaceable The NRC staff reviewed these design maintain its designed accuracy batteries used for instrument channel features prior to issuance of the following a power interruption or power shall have sufficient capacity to combined licenses for these facilities change in power source without maintain the level indication function and certification of the AP1000 design recalibration. 1.5 Display: The display shall until offsite resource availability is referenced therein. The AP1000 provide on-demand or continuous reasonably assured. certified design largely addresses the 1.7 Accuracy: The instrument requirements in Attachment 2 by indication of spent fuel pool water level. 2. The spent fuel pool channels shall maintain their designed providing two safety-related spent fuel instrumentation shall be maintained accuracy following a power interruption pool level instrument channels. The available and reliable through or change in power source without instruments measure level from the top appropriate development and recalibration. of the spent fuel pool to the top of the 1.8 Testing: The instrument channel fuel racks to address the range implementation of a training program. design shall provide for routine testing requirements listed above. The safety- Personnel shall be trained in the use and calibration. related classification provides for the and the provision of alternate power to 1.9 Display: Trained personnel shall following additional design features: the safety-related level instrument be able to monitor the spent fuel pool • Seismic and environmental channels. water level from the control room, qualification of the instruments [FR Doc. 2012–6550 Filed 3–16–12; 8:45 am] alternate shutdown panel, or other • Independent power supplies BILLING CODE 7590–01–P

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