ML113250200

Letter, Individual Notice of Consideration of Issuance of Amendment to Add New Surveillance Requirement 3.3.8.6 to Technical Specification 3.3.8, Emergency Exhaust System (EES) Actuation Instrumentation.

ML113250200
Person / Time
Site:	Callaway
Issue date:	11/22/2011
From:	Thadani M Plant Licensing Branch IV
To:	Heflin A Union Electric Co
Thadani, M C, NRR/DORL/LP4, 415-1476
References
TAC ME5173
Download: ML113250200 (17)

Text

{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 22, 2011 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251

SUBJECT:

CALLAWAY PLANT. UNIT 1 -INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR HEARING (TAC NO. ME5173)

Dear Mr. Heflin:

The U.S. Nuclear Regulatory Commission has forwarded the enclosed "Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," to the Office of the Federal Register for publication. This notice relates to your application dated December 10, 2010, as supplemented by letters dated June 16, 2011, and October 27, 2011. The license amendment request was originally noticed in the Federal Register on March 8, 2011 (76 FR 12766). This notice is being reissued in its entirety to include a revised description of the amendment request. The proposed amendment would add a new Surveillance Requirement (SR) 3.3.8.6 to Technical Specification (TS) 3.3.8, "Emergency Exhaust System (EES) Actuation Instrumentation." The new SR would require the performance of response time testing on the portion of the EES required to isolate the normal fuel building ventilation exhaust flow path and initiate the fuel building ventilation isolation signal (FBVIS) mode of operation. The proposed amendment also would revise TS Table 3.3.8-1 to indicate that new SR 3.3.8.6 applies to automatic actuation Function 2, "Automatic Actuation Logic and Actuation Relays (BOP ESFAS)," and Function 3, "Fuel Building Exhaust Radiation - Gaseous." In addition, the specified frequency of new SR 3.3.8.6 would be relocated and controlled in accordance with the licensee's Surveillance Frequency Control Program in accordance with guidance in Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical SpeCifications Initiative 5b, Risk Informed Method for Control of Surveillance Frequencies." Finally, there would be corresponding changes to the Final Safety Analysis Report (FSAH).

A. Heflin -2 If you have any questions, please contact me at 301-415-1476. Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483

Enclosure:

Notice of Consideration cc w/encl: Distribution via Listserv

[7590-01-P] NUCLEAR REGULATORY COMMISSION UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 [NRC-20XX-XXXXl NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FORA HEARING AGENCY: Nuclear Regulatory Commission. ACTION: Notice of license amendment request, opportunity to comment, opportunity to request a hearing. DATES: Comments must be filed by [INSERT DATE: 30 DAYS FROM DATE OF PUBLICATION OF THIS FEDERAL REGISTER NOTICE]. A request for a hearing must be filed [INSERT DATE: 60 DAYS FROM DATE OF PUBLICATION OF THIS FEDERAL REGISTER NOTICE]. ADDRESSES: Please include Docket ID NRC-XXXX-XXXX in the subject line of your comments. Comments submitted in writing or in electronic form will be posted on the NRC Web site and on the Federal rulemaking Web site http://www.regulations.gov. Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed.

                                             -2 The NRC requests that any party soliciting or aggregating comments received from other persons for submission to the NRC inform those persons that the NRC will not edit their comments to remove any identifying or contact information, and therefore, they should not include any information in their comments that they do not want publicly disclosed.

You may submit comments by anyone of the following methods. Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC-20XX-XXXX. Address questions about NRC dockets to Carol Gallagher 301-492-3668; e-mail CaroI.Galiagher@nrc.gov. Mail comments to: Chief, Rules, Announcements, and Directives Branch (RADB), Office of Administration, Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Fax comments to: RADB at 301-492-3446. You can access publicly available documents related to this notice using the following methods: NRC's Public Document Room (PDR): The public may examine and have copied, for a fee, publicly available documents at the NRC's PDR, 01-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are available online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain entry into ADAMS, which provides text and image files of the NRC's public documents. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the NRC's PDR reference staff at 1-800-397-4209, 301-415-4737, or bye-mail to pdr.resource@nrc.gov. The application for amendment, dated December 10,2010, as

                                                - 3 supplemented by letters dated June 16, 2011, and October 27, 2011, are available electronically under ADAMS Accession Nos. ML103470204, ML111680233, and ML113010383, respectively.

Federal Rulemaking Web Site: Public comments and supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID NRC-20XX XXXX. FOR FURTHER INFORMATION CONTACT: Mohan C. Thadani, Senior Project Manager, Plant Licensing Branch IV, Division of Operating Reactor licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone: 301 415-1476; fax number: 301-415-2102 e-mail: mohan.thadani@nrc.gov. The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-30 issued to Union Electric Company, (the licensee) for operation of the Callaway Plant, Unit 1, located in Callaway County, Missouri. The license amendment request was originally noticed in the Federal Register on March 8, 2011 (76 FR 12766). This notice is being reissued in its entirety to include a revised description of the amendment request. The proposed amendment would add a new Surveillance Requirement (SR) 3.3.8.6 to Technical Specification (TS) 3.3.8, "Emergency Exhaust System (EES) Actuation Instrumentation." The new SR would require the performance of response time testing on the portion of the EES required to isolate the normal fuel building ventilation exhaust flow path and initiate the fuel building ventilation isolation signal (FBVIS) mode of operation. The proposed amendment also would revise TS Table 3.3.8-1 to indicate that new SR 3.3.8.6 applies to automatic actuation Function 2, "Automatic Actuation Logic and Actuation Relays (BOP ESFAS)," and Function 3, "Fuel Building Exhaust Radiation - Gaseous." In addition, the specified frequency of new SR 3.3.8.6 would be relocated and controlled in accordance with the licensee's Surveillance Frequency Control Program in accordance with

                                                - 4 guidance in Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." Finally, there would be corresponding changes to the Final Safety Analysis Report (FSAR).

Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations. The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91{a), the licensee has provided its analysis of the issue of no significant hazards consideration, which the Commission issued in the Federal Register on March 8, 2011 (76 FR 12766). The Commission is issuing a modified no significant hazards consideration to consider aspects of the SR 3.3.8.6 relocation to the Surveillance Frequency Control Program. The NRC previously approved the relocation of surveillance frequencies as part of Callaway Plant's License Amendment No. 202, as noted in the Federal Register on January 11, 2011 (76 FR 1649).

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No. There are no design changes associated with the proposed change. All design, material, and construction standards that were applicable prior to this amendment request will continue to be applicable.

                                 - 5 The proposed change will not affect accident initiators or precursors nor adversely alter the design assumptions, conditions, and configuration of the facility or the manner in which the plant is operated and maintained with respect to such initiators or precursors. There will be no change to fuel handling methods and procedures. Therefore, there will be no changes that would serve to increase the likelihood of occurrence of a fuel handling accident.

The proposed change changes a performance requirement, but it does not physically alter safety-related systems nor affect the way in which safety-related systems perform their functions. The proposed TS change will serve to assure that the fuel building ventilation exhaust ESF [emergency safety feature] response time is tested and confirmed to be in accordance with the system design and consistent with the assumptions of the fuel building FHA [fuel handling accident] analysis (as revised). As such, the proposed change will not alter or prevent the capability of structures, systems, and components (SSCs) to perform their intended functions for mitigating the consequences of an accident and meeting applicable acceptance limits. The proposed change will not affect the source term used in evaluating the radiological consequences of a fuel handling accident in the fuel building. However, the Fuel Building Ventilation Exhaust ESF response time has been increased to 90 seconds in recognition of the total delay times involved in the generation of a fuel building ventilation isolation signal (FBVIS) and the times required for actuated components to change state to their required safety configurations. Consequently, the fuel handling accident radiological consequences as reported in FSAR [Final Safety Analysis Report] Table 15.7-8 have increased. However, the increases are much less than the upper limit of "minimal" as defined pursuant to 10 CFR 50.59(c)(2)(iii) and NEI [Nuclear Energy Institute] 96-07 Revision 1 ["Guidelines for 10 CFR 50.59 Implementation," November 2000]. Therefore, there is no significant increase in the calculated consequences of a postulated design basis fuel handling accident in the fuel building. The applicable radiological dose criteria of 10 CFR 100.11, 10 CFR 50 Appendix A General Design Criterion 19, and SRP [NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water-Reactor] Edition"] 15.7.4 will continue to be met. New SR 3.3.8.6 is added to ensure system performance consistent with the accident analyses and associated dose calculations (as revised). [The licensee's request in its letter dated October 27,2011, for relocating the specified frequency of new SR 3.3.8.6 to the licensee-controlled Surveillance Frequency Control Program is the type of SR whose relocation to the licensee's Surveillance Frequency Control Program was

                                   -6 previously approved in Amendment No. 202, dated July 29, 2011 (ADAMS Accession No. ML111661877). That amendment was approved based on the conclusion that the change did not involve a significant increase in the probability or consequences of accidents previously evaluated.]

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No. With respect to any new or different kind of accident, there are no proposed design changes nor are there any changes in the method by which any safety-related plant SSC performs its specified safety function. The proposed change will not affect the normal method of plant operation or change any operating parameters. No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of this amendment. The proposed amendment will not alter the design or performance of the 7300 Process Protection System, Nuclear Instrumentation System, Solid State Protection System, BOP ESFAS, MSFIS [Main Steam and Feed Isolation System], or LSELS [Load Shedding and Emergency Load Sequencing] used in the plant protection systems. [The licensee's request in its letter dated October 27,2011, for relocating the specified frequency of new SR 3.3.8.6 to the licensee-controlled Surveillance Frequency Control Program is the type of SR whose relocation to the licensee's Surveillance Frequency Control Program was previously approved in Amendment No. 202, dated July 29, 2011 (ADAMS Accession No. ML111661877). That amendment was approved based on the determination that the change does not involve a possibility of creating a new or different kind of accident]. The proposed change does not, therefore, create the possibility of a new or different accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No. There will be no effect on those plant systems necessary to assure the accomplishment of protection functions associated with reactor operation or the reactor coolant system. There will be no impact on the overpower

                                                -7 limit, departure from nucleate boiling ratio (DNBR) limits, heat flux hot channel factor (Fa), nuclear enthalpy rise hot channel factor (FilH), loss of coolant accident peak cladding temperature (LOCA PCT), peak local power density, or any other limit and associated margin of safety_

Required shutdown margins in the COLR [Core Operating Limits Report] will not be changed. The proposed change does not eliminate any surveillances or alter the frequency of surveillances required by the Technical Specifications. The proposed change would add a new Technical Specification Surveillance Requirement for assuring the satisfactory performance of the fuel building ventilation exhaust ESF function in response to a[n] FBVIS. The accident analysis for a fuel handling accident in the fuel building was re-performed to support the proposed Fuel Building Ventilation Exhaust ESF response time, and this reanalysis demonstrated that the acceptance criteria continue to be met with only a slight increase in radiological consequences (Le., less than one percent). [The licensee's request in its letter dated October 27,2011, for relocating the specified frequency of new SR 3.3.8.6 to the licensee-controlled Surveillance Frequency Control Program is the type of SR whose relocation to the licensee's Surveillance Frequency Control Program was previously approved in Amendment No. 202, dated July 29, 2011 (ADAMS Accession No. ML111661877). That amendment was approved based on the determination that the proposed change would not result in a significant reduction of margin of safety.] Therefore, the proposed change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60-day period provided that its final determination is that the

                                               - 8 amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30.;.day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently.

Written comments may be submitted by mail to the Chief, Rules, Announcements and Directives Branch (RADB), TWB-05-B01 M, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be faxed to the RADB at 301-492-3446. Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor). Rockville, Maryland. Within 60 days after the date of publication of this notice, any person(s) whose interest may be affected by this action may file a request for a hearing and a petition to intervene with respect to issuance of the amendment to the subject facility operating license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's "Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the Commission's PDR, located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. NRC regulations are accessible electronically from the NRC Library on the NRC Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or

                                                  -9 petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.

As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements: 1) the name, address and telephone number of the requestor or petitioner; 2) the nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding; 3) the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and 4) the possible effect of any decision or order which may be entered in the proceeding on the requestor's/petitioner's interest. The petition must also identify the specific contentions which the requestor/petitioner seeks to have litigated at the proceeding. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the requestor/petitioner shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The requestor/petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under

                                                - 10 consideration. The contention must be one which. if proven. would entitle the petitioner to relief.

A requestor/petitioner who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding. subject to any limitations in the order granting leave to intervene. and have the opportunity to participate fully in the conduct of the hearing. If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration. the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration. any hearing held would take place before the issuance of any amendment. All documents filed in NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene. any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities participating under 10 CFR 2.315{c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least ten (10) days prior to the filing deadline, the participant should contact the Office of the Secretary bye-mail at

                                                  - 11 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 http://www.nrc.gov/site-helo/e-submittals/apply-certificates.html. System requirements for accessing the E-Submittal server are detailed in NRC's "Guidance for Electronic Submission," which is available on the agency's public Web site at http://www.nrc.gov/site help/e-submittals.html. Participants may attempt to use other software not listed on the Web site, but should note that the NRC's E-Filing system does not support unlisted software, and the NRC Meta System Help Desk will not be able to offer assistance in using unlisted software. If a participant is electronically submitting a document to the NRC in accordance with the E-Filing rule, the participant must file the document using the NRC's online, Web-based submission form. In order to serve documents through EIE, users will be required to install a Web browser plug-in from the NRC Web site. Further information on the Web-based submission form, including the installation of the Web browser plug-in, is available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. Once a participant has obtained a 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

                                                - 12 available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.htmI.Afiling is considered complete at the time the documents are submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11 :59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt of the document. The E-Filing system also distributes an e-mail notice that provides access to the document to the NRC Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their counselor representative) must apply for and receive a digitallD certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system.

A person filing electronically using the agency's adjudicatory E-Filing system may seek assistance by contacting the NRC Meta System Help Desk through the "Contact Us" link located on the NRC Web site at http://www.nrc.gov/site-help/e-submittals.html.by e-mail at MSHD.Resource@nrc.gov, or by a toll-free call at (866) 672-7640. The NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern Time, Monday through Friday, excluding government holidays. Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) first class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service

                                                  - 13 to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants.

Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using E Filing. may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing docket which is available to the public at http://ehd1.nrc.gov/EHD/, unless excluded pursuant to an order of the Commission, or the presiding officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission. Petitions for leave to intervene must be filed no later than 60 days from the date of publication of this notice. Non-timely filings will not be entertained absent a determination by the presiding officer that the petition or request should be granted or the contentions should be admitted, based on a balancing of the factors specified in 10 CFR 2.309{c){1){i)-{viii). For further details with respect to this license amendment application, see the application for amendment dated December 10, 2010, as supplemented by letters dated June 16, 2011, and October 27, 2011, which is available for public inspection at the Commission's PDR, located at One White Flint North, File Public Area 01 F21, 11555 Rockville Pike (first

                                               - 14 floor), Rockville, Maryland. Publicly available documents created or received at the NRC are accessible electronically through ADAMS in the NRC Library at http://www.nrc.gov/reading rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or bye-mail to pdr.resource@nrc.gov.

Attorney for licensee: John O'Neill, Esq., Pillsbury Winthrop Shaw Pittman LLP, 2300 N Street, N.W., Washington, D.C. 20037. Dated at Rockville, Maryland, this 22nd day of November 2011. FOR THE NUCLEAR REGULATORY COMMISSION Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

A. Heflin - 2 If you have any questions, please contact me at 301-415-1476 .. Sincerely, IRN Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483

Enclosure:

Notice of Consideration cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC Branch Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMCallaway Resource RidsOgcRp Resource RidsRgn4MailCenter Resource ADAMS Accession Nos.: LTR ML113250200 FRN ML113250210 OFFICE NRR/DORULPL4/PM NRR/DORULPL4/LA NRR/DORULPL4/BC NRR/DORULPL4/PM NAME MThadani JBurkhardt MMarkley MThadani' DATE 11/21/11 11/21/11 11/22/11 11/22/11 OFFICIAL AGENCY RECORD}}