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Federally registered lobbyist possesses Associate Administrator for Diversity to an operating license upon a unique or exceptional value to a board and Equal Opportunity, NASA determination by the Commission that or commission? Headquarters such amendment involves no significant A12: The policy makes no provisions Assistant Administrator for Human hazards consideration, notwithstanding for waivers, and waivers will not be Capital Management, NASA the pendency before the Commission of permitted under this policy. Headquarters a request for a hearing from any person. Associate Administrator for This biweekly notice includes all Preeta D. Bansal, Independent Program and Cost notices of amendments issued, or OMB General Counsel and Senior Policy Evaluation, NASA Headquarters proposed to be issued from October 7, Advisor, Office of Management and Budget. Chief Engineer, NASA Headquarters 2010 to October 20, 2010. The last [FR Doc. 2010–27621 Filed 11–1–10; 8:45 am] General Counsel, NASA Headquarters biweekly notice was published on BILLING CODE P Chief Technologist, NASA Headquarters October 19, 2010 (75 FR 64359). Chief Scientist, NASA Headquarters Notice of Consideration of Issuance of Chief Information Officer, NASA Amendments to Facility Operating NATIONAL AERONAUTICS AND Headquarters SPACE ADMINISTRATION Licenses, Proposed No Significant Chief, Safety and Mission Assurance, Hazards Consideration Determination, [Notice (10–144)] NASA Headquarters and Opportunity for a Hearing Director, Ames Research Center Performance Review Board, Senior Director, Dryden Flight Research Center The Commission has made a Executive Service (SES) Director, Glenn Research Center proposed determination that the Director, Goddard Space Flight Center following amendment requests involve AGENCY: National Aeronautics and Director, Johnson Space Center no significant hazards consideration. Under the Commission’s regulations in Space Administration (NASA). Director, Kennedy Space Center Title 10 of the Code of Federal ACTION: Notice of Membership of SES Director, Langley Research Center Regulations (10 CFR), § 50.92, this Performance Review Board. Director, Marshall Space Flight Center means that operation of the facility in Director, Stennis Space Center SUMMARY: The Civil Service Reform Act accordance with the proposed of 1978, Public Law 95–454 (Section Senior Executive Committee amendment would not (1) involve a 405) requires that appointments of Chairperson, Deputy Administrator, significant increase in the probability or individual members to the Performance NASA Headquarters consequences of an accident previously Review Board (PRB) be published in the Chair, Executive Resources Board, evaluated; or (2) create the possibility of Federal Register. NASA Headquarters a new or different kind of accident from any accident previously evaluated; or The National Aeronautics and Space Chair, NASA Performance Review (3) involve a significant reduction in a Administration published a document Board, NASA Headquarters margin of safety. The basis for this in the Federal Register on October 12, Associate Administrator, NASA proposed determination for each 2010, announcing membership of the Headquarters Performance Review Board (PRB) and amendment request is shown below. Associate Deputy Administrator, NASA The Commission is seeking public the Senior Executive Committee. In Headquarters addition to the members previously comments on this proposed Chief Information Officer, NASA determination. Any comments received announced, another member was added Headquarters to the PRB, Associate Administrator for within 30 days after the date of Independent Program and Cost Charles F. Bolden, Jr., publication of this notice will be Evaluation. Administrator. considered in making any final [FR Doc. 2010–27551 Filed 11–1–10; 8:45 am] determination. Performance Review Board Normally, the Commission will not BILLING CODE P Chairperson, Chief of Staff, NASA issue the amendment until the Headquarters expiration of 60 days after the date of Executive Secretary, Director, Workforce publication of this notice. The NUCLEAR REGULATORY Management and Development Commission may issue the license COMMISSION Division, NASA Headquarters amendment before expiration of the 60- Associate Administrator, NASA [NRC–2010–0336] day period provided that its final Headquarters determination is that the amendment Associate Deputy Administrator, NASA Biweekly Notice; Applications and involves no significant hazards Headquarters Amendments to Facility Operating consideration. In addition, the Associate Administrator for Exploration Licenses Involving No Significant Commission may issue the amendment Systems Mission Directorate, NASA Hazards Considerations prior to the expiration of the 30-day Headquarters comment period should circumstances Associate Administrator for Space I. Background change during the 30-day comment Operations Mission Directorate, Pursuant to section 189a. (2) of the period such that failure to act in a NASA Headquarters Atomic Energy Act of 1954, as amended timely way would result, for example in Associate Administrator for Science (the Act), the U.S. Nuclear Regulatory derating or shutdown of the facility. Mission Directorate, NASA Commission (the Commission or NRC) Should the Commission take action Headquarters is publishing this regular biweekly prior to the expiration of either the Associate Administrator for Aeronautics notice. The Act requires the comment period or the notice period, it Research Mission Directorate, NASA Commission publish notice of any will publish in the Federal Register a Headquarters amendments issued, or proposed to be notice of issuance. Should the Associate Administrator for Mission issued and grants the Commission the Commission make a final No Significant Support Directorate, NASA authority to issue and make Hazards Consideration Determination, Headquarters immediately effective any amendment any hearing will take place after

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issuance. The Commission expects that nature of the requestor’s/petitioner’s All documents filed in NRC the need to take this action will occur right under the Act to be made a party adjudicatory proceedings, including a very infrequently. to the proceeding; (3) the nature and request for hearing, a petition for leave Written comments may be submitted extent of the requestor’s/petitioner’s to intervene, any motion or other by mail to the Chief, Rules, property, financial, or other interest in document filed in the proceeding prior Announcements and Directives Branch the proceeding; and (4) the possible to the submission of a request for (RADB), TWB–05–B01M, Division of effect of any decision or order which hearing or petition to intervene, and Administrative Services, Office of may be entered in the proceeding on the documents filed by interested Administration, U.S. Nuclear Regulatory requestor’s/petitioner’s interest. The governmental entities participating Commission, Washington, DC 20555– petition must also identify the specific under 10 CFR 2.315(c), must be filed in 0001, and should cite the publication contentions which the requestor/ accordance with the NRC E-Filing rule date and page number of this Federal petitioner seeks to have litigated at the (72 FR 49139, August 28, 2007). The E- Register notice. Written comments may proceeding. Filing process requires participants to also be faxed to the RADB at 301–492– Each contention must consist of a submit and serve all adjudicatory 3446. Documents may be examined, specific statement of the issue of law or documents over the internet, or in some and/or copied for a fee, at the NRC’s fact to be raised or controverted. In cases to mail copies on electronic Public Document Room (PDR), located addition, the requestor/petitioner shall storage media. Participants may not at One White Flint North, Public File provide a brief explanation of the bases submit paper copies of their filings Area O1F21, 11555 Rockville Pike (first for the contention and a concise unless they seek an exemption in floor), Rockville, Maryland. statement of the alleged facts or expert accordance with the procedures Within 60 days after the date of opinion which support the contention described below. publication of this notice, any person(s) and on which the requestor/petitioner To comply with the procedural whose interest may be affected by this intends to rely in proving the contention requirements of E-Filing, at least ten action may file a request for a hearing at the hearing. The requestor/petitioner (10) days prior to the filing deadline, the and a petition to intervene with respect must also provide references to those participant should contact the Office of to issuance of the amendment to the specific sources and documents of the Secretary by e-mail at subject facility operating license. which the petitioner is aware and on [email protected], or by telephone Requests for a hearing and a petition for which the requestor/petitioner intends at (301) 415–1677, to request (1) a leave to intervene shall be filed in to rely to establish those facts or expert digital ID certificate, which allows the accordance with the Commission’s opinion. The petition must include participant (or its counsel or ‘‘Rules of Practice for Domestic sufficient information to show that a representative) to digitally sign Licensing Proceedings’’ in 10 CFR Part documents and access the E-Submittal genuine dispute exists with the 2. Interested person(s) should consult a server for any proceeding in which it is applicant on a material issue of law or current copy of 10 CFR 2.309, which is participating; and (2) advise the fact. Contentions shall be limited to available at the Commission’s PDR, Secretary that the participant will be matters within the scope of the located at One White Flint North, Public submitting a request or petition for amendment under consideration. The File Area O1F21, 11555 Rockville Pike hearing (even in instances in which the contention must be one which, if (first floor), Rockville, Maryland. participant, or its counsel or proven, would entitle the requestor/ Publicly available records will be representative, already holds an NRC- petitioner to relief. A requestor/ accessible from the Agencywide issued digital ID certificate). Based upon petitioner who fails to satisfy these Documents Access and Management this information, the Secretary will System’s (ADAMS) Public Electronic requirements with respect to at least one establish an electronic docket for the Reading Room on the Internet at the contention will not be permitted to hearing in this proceeding if the NRC Web site, http://www.nrc.gov/ participate as a party. Secretary has not already established an reading-rm/doc-collections/cfr/. If a Those permitted to intervene become electronic docket. request for a hearing or petition for parties to the proceeding, subject to any Information about applying for a leave to intervene is filed by the above limitations in the order granting leave to digital ID certificate is available on date, the Commission or a presiding intervene, and have the opportunity to NRC’s public Web site at http:// officer designated by the Commission or participate fully in the conduct of the www.nrc.gov/site-help/e-submittals/ by the Chief Administrative Judge of the hearing. apply-certificates.html. System Atomic Safety and Licensing Board If a hearing is requested, the requirements for accessing the E- Panel, will rule on the request and/or Commission will make a final Submittal server are detailed in NRC’s petition; and the Secretary or the Chief determination on the issue of no ‘‘Guidance for Electronic Submission,’’ Administrative Judge of the Atomic significant hazards consideration. The which is available on the agency’s Safety and Licensing Board will issue a final determination will serve to decide public Web site at http://www.nrc.gov/ notice of a hearing or an appropriate when the hearing is held. If the final site-help/e-submittals.html. Participants order. determination is that the amendment may attempt to use other software not As required by 10 CFR 2.309, a request involves no significant hazards listed on the Web site, but should note petition for leave to intervene shall set consideration, the Commission may that the NRC’s E-Filing system does not forth with particularity the interest of issue the amendment and make it support unlisted software, and the NRC the petitioner in the proceeding, and immediately effective, notwithstanding Meta System Help Desk will not be able how that interest may be affected by the the request for a hearing. Any hearing to offer assistance in using unlisted results of the proceeding. The petition held would take place after issuance of software. should specifically explain the reasons the amendment. If the final If a participant is electronically why intervention should be permitted determination is that the amendment submitting a document to the NRC in with particular reference to the request involves a significant hazards accordance with the E-Filing rule, the following general requirements: (1) The consideration, any hearing held would participant must file the document name, address, and telephone number of take place before the issuance of any using the NRC’s online, Web-based the requestor or petitioner; (2) the amendment. submission form. In order to serve

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documents through EIE, users will be Commission, U.S. Nuclear Regulatory access to ADAMS or who encounter required to install a Web browser plug- Commission, Washington, DC 20555– problems in accessing the documents in from the NRC Web site. Further 0001, Attention: Rulemaking and located in ADAMS, should contact the information on the Web-based Adjudications Staff; or (2) courier, NRC PDR Reference staff at 1–800–397– submission form, including the express mail, or expedited delivery 4209, 301–415–4737, or by e-mail to installation of the Web browser plug-in, service to the Office of the Secretary, [email protected]. is available on the NRC’s public Web Sixteenth Floor, One White Flint North, site at http://www.nrc.gov/site-help/e- 11555 Rockville Pike, Rockville, Entergy Operations, Inc., Docket No. 50– submittals.html. Maryland 20852, Attention: Rulemaking 313, Arkansas Nuclear One, Unit No. 1 Once a participant has obtained a and Adjudications Staff. Participants (ANO–1), Pope County, Arkansas digital ID certificate and a docket has filing a document in this manner are Date of amendment request: August been created, the participant can then responsible for serving the document on 24, 2010. submit a request for hearing or petition all other participants. Filing is Description of amendment request: for leave to intervene. Submissions considered complete by first-class mail The proposed amendment would revise should be in Portable Document Format as of the time of deposit in the mail, or Technical Specifications (TSs) 3.4.6, (PDF) in accordance with NRC guidance by courier, express mail, or expedited ‘‘RCS Loops—Mode 4,’’ TS 3.4.7, ‘‘RCS available on the NRC public Web site at delivery service upon depositing the Loops—Mode 5, Loops Filled,’’ TS 3.4.8, http://www.nrc.gov/site-help/e- document with the provider of the ‘‘RCS Loops—Mode 5, Loops Not submittals.html. A filing is considered service. A presiding officer, having Filled,’’ and TS 3.9.5, ‘‘Decay Heat complete at the time the documents are granted an exemption request from Removal (DHR) and Coolant submitted through the NRC’s E-Filing using E-Filing, may require a participant Circulation—Low Water Level,’’ to system. To be timely, an electronic or party to use E-Filing if the presiding permit a greater time period for one of filing must be submitted to the E-Filing officer subsequently determines that the two required Reactor Coolant System system no later than 11:59 p.m. Eastern reason for granting the exemption from (RCS) cooling loops (commonly known Time on the due date. Upon receipt of use of E-Filing no longer exists. as Decay Heat Removal loop) cooling a transmission, the E-Filing system Documents submitted in adjudicatory loops to be inoperable. The affected TSs time-stamps the document and sends proceedings will appear in NRC’s are applicable in lower Modes of the submitter an e-mail notice electronic hearing docket which is Operation (Modes 4, 5, and 6). confirming receipt of the document. The available to the public at http:// Basis for proposed no significant E-Filing system also distributes an e- ehd.nrc.gov/EHD_Proceeding/home.asp, hazards consideration determination: mail notice that provides access to the unless excluded pursuant to an order of As required by 10 CFR 50.91(a), the document to the NRC Office of the the Commission, or the presiding licensee has provided its analysis of the General Counsel and any others who officer. Participants are requested not to issue of no significant hazards have advised the Office of the Secretary include personal privacy information, consideration, which is presented that they wish to participate in the such as social security numbers, home below: proceeding, so that the filer need not addresses, or home phone numbers in 1. Does the proposed change involve a serve the documents on those their filings, unless an NRC regulation significant increase in the probability or participants separately. Therefore, or other law requires submission of such consequences of an accident previously applicants and other participants (or information. With respect to evaluated? their counsel or representative) must copyrighted works, except for limited Response: No. apply for and receive a digital ID excerpts that serve the purpose of the The proposed change does not involve any certificate before a hearing request/ adjudicatory filings and would physical change to the plant and is unrelated petition to intervene is filed so that they constitute a Fair Use application, to accident initiators. In Mode 4, the energy can obtain access to the document via participants are requested not to include contained in the RCS is significantly reduced from that of power operations. In addition, the E-Filing system. copyrighted materials in their RCS pressure can be raised or lowered to A person filing electronically using submission. accommodate forced circulation using the agency’s adjudicatory E-Filing Petitions for leave to intervene must Reactor Coolant Pumps (RCPs) or operation system may seek assistance by be filed no later than 60 days from the of the Decay Heat Removal (DHR) system. contacting the NRC Meta System Help date of publication of this notice. Non- Natural circulation also provides a core heat Desk through the ‘‘Contact Us’’ link timely filings will not be entertained removal method via any available Steam located on the NRC Web site at http:// absent a determination by the presiding Generator (SG). Several sources of secondary www.nrc.gov/site-help/e- officer that the petition or request feedwater are, or could be made available to submittals.html, by e-mail at should be granted or the contentions a required SG in support of forced circulation [email protected], or by a toll- should be admitted, based on a or natural circulation. Based on this information, any mitigation strategy which free call at (866) 672–7640. The NRC balancing of the factors specified in 10 assumes use of these core cooling methods is Meta System Help Desk is available CFR 2.309(c)(1)(i)–(viii). not significantly affected by the proposed between 8 a.m. and 8 p.m., Eastern For further details with respect to this increase in the time in which one required Time, Monday through Friday, license amendment application, see the train may be inoperable. excluding government holidays. application for amendment which is No accidents associated with the reactor Participants who believe that they available for public inspection at the core or core cooling are postulated for Mode have a good cause for not submitting Commission’s PDR, located at One 5. In Mode 6, the fuel handling accident documents electronically must file an White Flint North, Public File Area (FHA) is the only postulated accident exemption request, in accordance with O1F21, 11555 Rockville Pike (first scenario. The proposed change has no 10 CFR 2.302(g), with their initial paper floor), Rockville, Maryland. Publicly bearing on the FHA from either an initiation aspect or with regard to accident filing requesting authorization to available records will be accessible from consequences. continue to submit documents in paper the ADAMS Public Electronic Reading Based on the above, the proposed change format. Such filings must be submitted Room on the Internet at the NRC Web does not involve a significant increase in the by: (1) First class mail addressed to the site, http://www.nrc.gov/reading-rm/ probability or consequences of an accident Office of the Secretary of the adams.html. Persons who do not have previously evaluated.

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2. Does the proposed change create the Description of amendment request: The proposed changes do not impact any possibility of a new or different kind of The proposed amendment involves safety analysis assumptions and do not accident from any accident previously administrative changes to the Technical involve a change in initial conditions, system evaluated? response times, or other parameters affecting Response: No. Specifications (TSs). The proposed an accident analysis. The proposed change only extends the changes involve: (1) Making an editorial Therefore, the proposed changes do not period in which one of two required core change to LGS Unit 1 TS Limiting involve a significant reduction in a margin of heat removal methods may be unavailable. Condition for Operation (LCO) 3.3.1, safety. The proposed change involves no changes to Action b; (2) making an editorial change The NRC staff has reviewed the the physical plant and is not associated with to LGS Units 1 and 2 TS Table 3.3.1– any accident initiator. licensee’s analysis and, based on this 1, Actions 2 and 9; (3) making the layout review, it appears that the three Based on the above, the proposed change and format of LGS Unit 1 TS LCO does not create the possibility of a new or standards of 10 CFR 50.92(c) are different kind of accident from any 3.6.5.3 Action requirements consistent satisfied. Therefore, the NRC staff previously evaluated. with the LGS Unit 2 LCO Action proposes to determine that the 3. Does the proposed change involve a requirements for the same TS; and amendment request involves no significant reduction in a margin of safety? (4) adding a reference to the minimum significant hazards consideration. Response: No. required number of operable main Attorney for licensee: J. Bradley As discussed above, the proposed change turbine bypass valves and the turbine Fewell, Esquire, Associate General is unrelated to accident initiators and does bypass system response time to the core not have a significant impact on the Counsel, Exelon Generation Company, consequences of any accident previously operating limits documented in the Core LLC, 4300 Winfield Road, Warrenville, evaluated in the ANO–1 Safety Analysis Operating Limits Report as specified in IL 60555. Report (SAR). The proposed change extends LGS, Units 1 and 2, TS 6.9.1.9. NRC Branch Chief: Harold K. the time in which one of two required core Basis for proposed no significant Chernoff. heat removal methods may be unavailable. In hazards consideration determination: most cases, more than one additional cooling As required by 10 CFR 50.91(a), the Exelon Generation Company, LLC, method remains available. In addition, licensee (Exelon) has provided its Docket No. 50–219, Oyster Creek proceduralized administrative controls act to analysis of the issue of no significant Nuclear Generating Station, Ocean protect remaining required equipment hazards consideration, which is County, New Jersey (including inventory makeup sources) and to prevent removal of important equipment presented below: Date of amendment request: June 11, from service during higher risk plant 1. Do the proposed changes involve a 2010. configurations (such as reduced inventory significant increase in the probability or Description of amendment request: conditions). consequences of an accident previously The amendment would revise the In Mode 5 and 6, the idle cooling loop may evaluated? Oyster Creek Nuclear Generating Station only be made unavailable in support of Response: No. The proposed changes are Technical Specifications (TSs), surveillance testing and only if the remaining administrative in nature and do not impact Appendix B. Specifically, the proposed the physical configuration or function of loop is operable and in operation. amendment would change some Additionally, the idle cooling loop can be plant structures, systems, or components made unavailable only if it can be recovered (SSCs) or the manner in which SSCs are wording to align with the Exelon within the calculated time-to-boil for the operated, maintained, modified, tested, or Generation Company (EGC) most restrictive plant configuration that may inspected. The proposed changes do not terminology. Additionally, the proposed exist during the test window. These impact the initiators or assumptions of amendment would revise the restrictions, along with the information in the analyzed events, nor do they impact description of the review and audit preceding paragraph, maintain a sufficient mitigation of accidents or transient events. function to align with the EGC fleet margin to safety to preclude a challenge to Therefore, the proposed changes do not model and relocate scope of the audit to involve a significant increase in the the integrity of the fuel clad. the EGC fleet-wide Quality Assurance Therefore, the proposed change does not probability or consequences of an accident involve a significant reduction in the margin previously evaluated. Topical Report. to safety. 2. Do the proposed changes create the Basis for proposed no significant possibility of a new or different kind of hazards consideration determination: The NRC staff has reviewed the accident from any accident previously As required by 10 CFR 50.91(a), the licensee’s analysis and, based on this evaluated? licensee has provided its analysis of the review, it appears that the three Response: No. The proposed changes are issue of no significant hazards standards of 10 CFR 50.92(c) are administrative in nature and do not alter consideration, which is presented plant configuration, require that new plant satisfied. Therefore, the NRC staff below: proposes to determine that the equipment be installed, alter assumptions amendment request involves no made about accidents previously evaluated, 1. [The proposed changes do not involve a or impact the function of plant SSCs or the significant increase in the probability or significant hazards consideration. manner in which SSCs are operated, consequences of an accident previously Attorney for licensee: Joseph A. maintained, modified, tested, or inspected. evaluated.] Aluise, Associate General Counsel— Therefore, the proposed changes do not Response: No. Nuclear, Entergy Services, Inc., 639 create the possibility of a new or different The Environmental Technical Loyola Avenue, New Orleans, Louisiana kind of accident from any accident Specifications (ETS) are concerned with 70113. previously evaluated. monitoring the effect that plant operations NRC Branch Chief: Michael T. 3. Do the proposed changes involve a have on the environment for the purpose of Markley. significant reduction in a margin of safety? protecting the environment and have no Response: No. The proposed changes are [effect] on any accident postulated in the Exelon Generation Company, LLC, administrative in nature and do not involve Updated Final Safety Analysis Report Docket Nos. 50–352 and 50–353, any physical changes to plant SSCs or the (UFSAR). Accident probabilities or Limerick Generating Station (LGS), manner in which SSCs are operated, consequences are not affected in any way by Units 1 and 2, Montgomery County, maintained, modified, tested, or inspected. the environmental monitoring and reporting Pennsylvania The proposed changes do not involve a required by the ETS. The revision of portions change to any safety limits, limiting safety of Appendix B of the Renewed Facility Date of amendment request: August system settings, limiting conditions for Operating License (FOL) will not impact the 31, 2010. operation, or design parameters for any SSC. design or operation of any plant system or

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component. No environmental protection Therefore, the proposed changes do not Therefore, the proposed change does not requirements established by other Federal, involve a significant reduction in a margin of involve a significant increase in the State, or local agencies are being reduced by safety. probability or consequences of an accident previously evaluated. this license amendment request. The NRC staff has reviewed the No physical changes to Oyster Creek 2. The proposed change does not create the Nuclear Generating Station (OCNGS) will licensee’s analysis and, based on this possibility of a new or different kind of occur as a result of this proposed review, and with the changes noted accident from any accident previously amendment. The proposed changes will not above in square brackets, it appears that evaluated. alter the physical design or operational the three standards of 10 CFR 50.92(c) The proposed change will not impact the procedures associated with any plant are satisfied. Therefore, the NRC staff accident analysis. The change does not structure, system, or component. proposes to determine that the involve a physical alteration of the plant (i.e., The proposed changes involve the amendment request involves no no new or different type of equipment will revision/relocation of administrative significant hazards consideration. be installed), a significant change in the requirements from the Environmental method of plant operation, or new operator Attorney for licensee: Mr. J. Bradley actions. The proposed change will not Technical Specifications (ETS) that are now Fewell, Associate General Counsel, controlled under the EGC Quality Assurance introduce failure modes that could result in Topical Report (QATR). The Technical Exelon Generation Company LLC, 4300 a new accident. The change does not alter Specification (TS) requirements involve Winfield Road, Warrenville, IL 60555. assumptions made in the safety analysis. Organization and Audit and Review. NRC Branch Chief: Harold Chernoff. Therefore, the proposed change does not create the possibility of a new or different Therefore, the proposed changes do not NextEra Energy Seabrook, LLC Docket involve a significant increase in the kind of accident from any accident probability or consequences of an accident No. 50–443, Seabrook Station, Unit No. previously evaluated. previously evaluated. 1, Rockingham County, New Hampshire 3. The proposed change does not involve 2. [The proposed changes do not create the Date of amendment request: June 28, a significant reduction in a margin of safety. Margin of safety is associated with possibility of a new or different kind of 2010. accident from any previously evaluated.] confidence in the ability of the fission Description of amendment request: product barriers (i.e., fuel cladding, reactor Response: No. The proposed change would delete the Environmental monitoring and reporting coolant system pressure boundary, and have no effect on accident initiation. The Seabrook Technical Specification containment structure) to limit the level of revision of portions of Appendix B of the 3.8.4.2, ‘‘Containment Penetration radiation dose to the public. The proposed OCNGS TS[s] will not impact the design or Conductor Overcurrent Protective change does not involve a significant change operation of any plant system or component. Devices and Protective Devices for Class in the method of plant operation, and no There will be no effect on the types or 1E Power Sources Connected to Non- accident analyses will be affected by the amount of any effluents released from the Class 1E Circuits.’’ The requirements proposed changes. Additionally, the plant. proposed changes will not relax any criteria would be relocated to a licensee- used to establish safety limits and will not The proposed changes do not alter the controlled document, the Technical physical design, safety limits, or safety relax any safety system settings. The safety Requirements Manual (TRM). analysis acceptance criteria are not affected analysis assumptions associated with the Basis for proposed NSHC operation of the plant. Accordingly, the by this change. The proposed change will not changes do not introduce any new accident determination: As required by 10 CFR result in plant operation in a configuration outside the design basis. The proposed initiators, nor do they reduce or adversely 50.91(a), the licensee has provided its change does not adversely affect systems that [effect] the capabilities of any plant structure, analysis of the issue of NSHC, which is respond to safely shutdown the plant and to system, or component to perform their safety presented below: maintain the plant in a safe shutdown function. 1. The proposed change does not involve condition. Therefore, the proposed changes do not a significant increase in the probability or Therefore, these proposed changes do not create the possibility of a new or different consequences of an accident previously involve a significant reduction in a margin of kind of accident from any accident evaluated. safety. previously evaluated. The proposed change does not impact the 3. [The proposed changes do not involve a physical function of plant structures, The NRC staff has reviewed the significant reduction in the margin of safety.] systems, or components (SSCs) or the manner licensee’s analysis and, based on this Response: No. in which SSCs perform their design function. review, it appears that the three Revision of the ETS Organization and The proposed change neither adversely standards of 50.92(c) are satisfied. Audit and Review criteria in accordance with affects accident initiators or precursors, nor Therefore, the NRC staff proposes to this submittal has no impact on margin of alters design assumptions. The proposed determine that the amendment request safety. Environmental evaluations will still change does not alter or prevent the ability be performed, when necessary, on changes to involves NSHC. of operable SSCs to perform their intended Attorney for licensee: M.S. Ross, plant design or operations to assess the effect function to mitigate the consequences of an on environmental protection. Review, initiating event within assumed acceptance Florida Power & Light Company, P.O. analysis and investigation of Unusual and limits. Box 14000, Juno Beach, FL 33408–0420. Important Environmental Events will still be This proposed change relocates the NRC Branch Chief: Harold K. performed in accordance with the EGC requirements for the containment penetration Chernoff. Corrective Action Program. conductor overcurrent protective devices and Northern States Power Company— The proposed changes conform to NRC the protective devices for Class 1E power regulatory guidance regarding the content of sources connected to non-Class 1E circuits to Minnesota, Docket No. 50–263, plant [TSs]. The guidance is presented in 10 the TRM. Relocating these requirements will Monticello Nuclear Generating Plant CFR 50.36 and NUREG–1433. The revision of have no adverse effect on plant operation, the (MNGP), Wright County, Minnesota these administrative requirements will not availability or operation of any accident Date of amendment request: reduce the quality assurance commitments as mitigation equipment, or plant response to a September 17, 2010. accepted by the NRC, nor reduce design basis accident. The electrical Description of amendment request: administrative controls essential to the safe protective devices are not accident initiators. operation of the plant. Future changes to Whether the requirements for penetration The licensee proposed to amend the these administrative requirements will be protective devices for 1E power sources are MNGP Technical Specifications, performed in accordance with NRC contained in the TS or the TRM has no effect revising the values for the Minimum regulation 10 CFR 50.54(a), consistent with on the probability or consequences of any Critical Power Ratio (MCPR) safety the guidance identified above. accident previously evaluated. limits of Reactor Core Safety Limit

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2.1.1.2. Currently this specification says methods, scenarios, acceptance criteria, or Maryland. Publicly available records ‘‘MCPR shall be ≥1.10 for two assumptions. Therefore, the proposed will be accessible from the Agencywide recirculation loop operation or ≥1.12 for amendment does not involve a significant Documents Access and Management single recirculation loop operation.’’ The reduction in a margin of safety. System (ADAMS) Public Electronic proposed amendment will change this The NRC staff has reviewed the Reading Room on the internet at the specification to read ‘‘MCPR shall be licensee’s analysis and, based on this NRC Web site, http://www.nrc.gov/ ≥1.15 for two recirculation loop review, it appears that the three reading-rm/adams.html. If you do not operation or ≥1.15 for single standards of 10 CFR 50.92(c) are have access to ADAMS or if there are recirculation loop operation.’’ The basis satisfied. Therefore, the NRC staff problems in accessing the documents of the MCPR safety limit is to ensure proposes to determine that the proposed located in ADAMS, contact the PDR that during normal operation and during amendment involves no significant Reference staff at 1 (800) 397–4209, abnormal operational transients, at least hazards consideration. (301) 415–4737 or by e-mail to 99.9 percent of all fuel rods in the core Attorney for the licensee: Peter M. [email protected]. do not experience transition boiling if Glass, Assistant General Counsel, Xcel Entergy Nuclear Vermont Yankee, LLC the limit is not violated. The licensee’s Energy Services, Inc., 414 Nicollet Mall, and Entergy Nuclear Operations, Inc., proposed MCPR safety limit values, Minneapolis, MN 55401 Docket No. 50–271, Vermont Yankee when approved by the NRC staff, will NRC Branch Chief: Robert J. Nuclear Power Station, Vernon, preserve the existing margin to Pascarelli. Vermont transition boiling, thus ensuring that the Notice of Issuance of Amendments to probability of fuel damage will not be Facility Operating Licenses Date of amendment request: December 3, 2009. increased. During the period since publication of Basis for proposed no significant Description of amendment request: the last biweekly notice, the hazards consideration determination: This amendment request revises Commission has issued the following As required by 10 CFR 50.91(a), the Technical Specifications to incorporate amendments. The Commission has licensee has provided its analysis of the Standard Technical Specification 3.1.8 determined for each of these issue of no significant hazards ‘‘Scram Discharge Volume (SDV) Vent amendments that the application consideration (NSHC) analysis. The and Drain Valves’’ and associated Bases complies with the standards and NRC staff reviewed the licensee’s NSHC of NUREG–1433, Revision 3, ‘‘Standard requirements of the Atomic Energy Act analysis and has prepared its own as Technical Specifications General of 1954, as amended (the Act), and the follows: Electric Plants, BWR/4,’’ modified to Commission’s rules and regulations. (1) Does the proposed amendment involve account for plant specific design details. The Commission has made appropriate Date of Issuance: October 6, 2010. a significant increase in the probability or findings as required by the Act and the consequences of an accident previously Effective date: As of the date of evaluated? Commission’s rules and regulations in issuance, and shall be implemented Response: No. 10 CFR chapter I, which are set forth in within 60 days. The purpose of the MCPR safety limits is the license amendment. Amendment No.: 244. to ensure that at least 99.9 percent of all fuel Notice of Consideration of Issuance of Facility Operating License No. DPR– rods in the core do not experience transition Amendment to Facility Operating 28: Amendment revised the License and boiling if the limit is not violated. Of the License, Proposed No Significant Technical Specifications. postulated accidents and transients Hazards Consideration Determination, Date of initial notice in Federal previously analyzed in the MNGP Updated and Opportunity for A Hearing in Safety Analysis Report, none of them were Register: April 6, 2010 (75 FR 17444). postulated to be initiated by operation within connection with these actions was The Commission’s related evaluation the approved MCPR safety limits. published in the Federal Register as of this amendment is contained in a Furthermore, the consequences of the indicated. Safety Evaluation dated October 6, 2010. analyzed accidents were not postulated to be Unless otherwise indicated, the No significant hazards consideration exacerbated by operation within approved Commission has determined that these comments received: No. MCPR safety limits. Accordingly, the amendments satisfy the criteria for probability of occurrence and the categorical exclusion in accordance Entergy Operations, Inc., Docket No. 50– consequences of the previously analyzed with 10 CFR 51.22. Therefore, pursuant 382, Waterford Steam Electric Station, accidents would not be affected in any way Unit 3, St. Charles Parish, Louisiana by the proposed amendment to the TS. to 10 CFR 51.22(b), no environmental (2) Does the proposed amendment create impact statement or environmental Date of amendment request: February the possibility of a new or different kind of assessment need be prepared for these 24, 2010. accident from any accident previously amendments. If the Commission has Brief description of amendment: The evaluated? prepared an environmental assessment amendment deleted Operating License Response: No. under the special circumstances Condition 2.C.14, Fuel Movement in the The proposed amendment does not involve provision in 10 CFR 51.22(b) and has Fuel Handling Building, due to the any physical alteration of the plant (no new made a determination based on that licensee’s election to comply with 10 or different type of equipment will be ‘‘ installed) nor does it change methods and assessment, it is so indicated. CFR 50.68, Criticality accident procedures governing plant operation. The For further details with respect to the requirements,’’ of Title 10 of the Code of proposed amendment will not impose any action see (1) the applications for Federal Regulations (10 CFR). License new or eliminate any old requirements. amendment, (2) the amendment, and Condition 2.C.14, which essentially Therefore, the proposed amendment does not (3) the Commission’s related letter, requires that no more than one fuel create the possibility of a new or different Safety Evaluation and/or Environmental assembly shall be out of its shipping kind of accident from any previously Assessment as indicated. All of these container or storage location at a given evaluated. items are available for public inspection time, was one basis for the licensee’s (3) Does the proposed amendment involve a significant reduction in a margin of safety? at the Commission’s Public Document previous exemption from the criticality Response: No. Room (PDR), located at One White Flint alarm system requirements of 10 CFR The proposed amendment will not have North, Public File Area 01F21, 11555 70.24. The criticality accident any effect on previously used safety analysis Rockville Pike (first floor), Rockville, requirements can be met either by

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complying with 10 CFR 70.24 or 10 CFR PSEG Nuclear LLC, Docket No. 50–354, American Society of Mechanical 50.68 requirements. The 10 CFR 50.68 Hope Creek Generating Station, Salem Engineers Boiler and Pressure Vessel criteria are now being used; therefore, County, New Jersey Code Class 1, 2 and 3 components; (2) License Condition 2.C.14 is no longer Date of application for amendment: add a new TS for the IST Program to ‘‘ ’’ required. December 21, 2009, as supplemented by Section 6.0, Administrative Controls, Date of issuance: October 14, 2010. letters dated May 11, June 10, June 24, of the TSs; (3) change TSs that currently Effective date: As of the date of reference TS 4.0.5 to reference the IST June 29, July 28, August 3, August 12, issuance and shall be implemented 60 Program or ISI Program, as applicable; September 10, and September 17, 2010. days from the date of issuance. and (4) revise TS 6.10.3.h to reflect the Brief description of amendment: The Amendment No.: 229. deletion of the ISI Program from the amendment allows the production of Facility Operating License No. NPF– TSs. 38: The amendment revised the Facility Cobalt-60 by irradiating Cobalt-59 Date of issuance: October 19, 2010. Operating License and Technical targets located in modified fuel Effective date: As of the date of Specifications. assemblies called Isotope Test issuance, to be implemented within 60 Date of initial notice in Federal Assemblies (ITAs). The amendment days. Register: May 4, 2010 (75 FR 23813). allows up to 12 ITAs to be loaded into Amendment No.: 185. The Commission’s related evaluation the reactor core beginning with the fall Facility Operating License No. NPF– of the amendment is contained in a 2010 refueling outage. The modified 57: The amendment revised the TSs and Safety Evaluation dated October 14, fuel assemblies are planned to be in the License. 2010. operation as part of a pilot program. The Date of initial notice in Federal No significant hazards consideration purpose of the pilot program is to obtain Register: January 26, 2010 (75 FR comments received: No. data to verify that the modified fuel 4118). assemblies perform satisfactorily in The Commission’s related evaluation Exelon Generating Company, LLC, service prior to use on a production of the amendment is contained in a Docket No. 50–219, Oyster Creek basis. The Cobalt-60 is ultimately Safety Evaluation dated October 19, Nuclear Generating Station, Ocean intended for use in the medical industry 2010. County, New Jersey for use in cancer treatments, and blood No significant hazards consideration Date of application for amendment: and instrument sterilization; in the comments received: No. February 25, 2010, as supplemented by radiography and security industries for Southern California Edison Company, et letters dated July 9, October 14, and imaging; and in the food industry for al., Docket Nos. 50–361 and 50–362, October 15, 2010. cold pasteurization and irradiation San Onofre Nuclear Generating Station, Brief description of amendment: The sterilization. Units 2 and 3, San Diego County, amendment revises the Technical Date of issuance: October 7, 2010. California Specifications to allow temporary Effective date: As of the date of Date of application for amendment: changes to the Secondary Containment issuance, to be implemented within 45 days. August 16, 2010. boundary during shutdown conditions. Brief description of amendment: The Specifically, the change allows the Amendment No.: 184. Facility Operating License No. NPF– amendments revised Technical Reactor Building Secondary ‘‘ 57: The amendment revised the Specification 3.8.1, AC [Alternating Containment boundary associated with ’’ Technical Specifications and the Current] Sources—Operating, the Trunnion Room to be relocated from Condition A, to allow a one-time the Trunnion Room outer wall and door License. Date of initial notice in Federal extension of the Completion Time (per to the Reactor Building inner walls and train) to 10 days to restore an inoperable penetrations located inside the Register: March 2, 2010 (75 FR 9445). The letters dated May 11, June 10, June required offsite circuit. Trunnion Room. Date of issuance: October 15, 2010. Date of issuance: October 18, 2010. 24, June 29, July 28, August 3, August Effective date: Upon issuance; to be Effective date: As of its date of 12, September 10, and September 17, implemented within 60 days of issuance, and shall be implemented 2010, provided clarifying information issuance. within 60 days. that did not change the initial proposed Amendment No.: Unit 2–224; Unit 3– Amendment No.: 277. no significant hazards consideration 217. Renewed Facility Operating License determination or expand the application Facility Operating License Nos. NPF– No. DPR–16: The amendment revised beyond the scope of the original Federal 10 and NPF–15: The amendment the License and Technical Register notice. revised the Operating Licenses and Specifications The Commission’s related evaluation Technical Specifications. Date of initial notice in Federal of the amendment is contained in a Date of initial notice in Federal Register: June 8, 2010 (75 FR 32513). Safety Evaluation dated October 7, 2010. Register: September 7, 2010 (75 FR The supplements dated July 9, October No significant hazards consideration 54395). 14, and October 15, 2010, provided comments received: Yes. No significant hazards consideration additional information that clarified the PSEG Nuclear LLC, Docket No. 50–354, (NSHC) comments received: No. application, did not expand the scope of Hope Creek Generating Station, Salem The Commission’s related evaluation the application as originally noticed, County, New Jersey of the amendments, state consultation, and did not change the NRC staff’s and final NSHC determination is original proposed no significant hazards Date of application for amendment: contained in a Safety Evaluation dated determination. November 4, 2009. October 15, 2010. The Commission’s related evaluation Brief description of amendment: The Attorney for licensee: Douglas K. of the amendment is contained in a amendment revises the Technical Porter, Esquire, Southern California Safety Evaluation dated October 18, Specifications (TSs) to: (1) Delete TS Edison Company, 2244 Walnut Grove 2010. 4.0.5, which pertains to surveillance Avenue, Rosemead, California 91770. No significant hazards consideration requirements for inservice inspection NRC Branch Chief: Michael T. comments received: No. (ISI) and inservice testing (IST) of Markley.

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Virginia Electric and Power Company, et For the Nuclear Regulatory Commission. preparation of the EIS on the proposed al., Docket Nos. 50–280 and 50–281, Joseph G. Giitter, action to comply with Section 106 of the Surry Power Station, Units 1 and 2, Director, Division of Operating Reactor NHPA in lieu of the procedures set forth Surry County, Virginia Licensing, Office of Nuclear Reactor in 36 CFR 800.3 through 800.6. Regulation. In accordance with 10 CFR 51.45 and Date of application for amendments: [FR Doc. 2010–27416 Filed 11–1–10; 8:45 am] 51.50, Exelon submitted the ER as part October 16, 2009, as supplemented by BILLING CODE 7590–01–P of the ESP application. The ER was letter dated May 7, 2010. prepared pursuant to 10 CFR parts 51 Brief Description of amendments: and 52 and is available for public These amendments revised the NUCLEAR REGULATORY inspection at the NRC Public Document Technical Specifications (TSs) to: COMMISSION Room (PDR) located at One White Flint (1) Implementation of WCAP–8745– [Docket No. 52–042; NRC–2010–0165] North, 11555 Rockville Pike (first floor), P–A, ‘‘Design Bases for Thermal Rockville, Maryland 20852 or from the Overpower Delta-T and Thermal Exelon Nuclear Texas Holdings, LLC; Publicly Available Records (PAR) Overtemperature Delta-T Trip Victoria County Station Early Site component of NRC’s Agencywide Function,’’ Permit Application; Notice of Intent To Documents Access and Management (2) Implementation of NRC-approved Prepare an Environmental Impact System (ADAMS). ADAMS is accessible Dominion Fleet Report DOM–NAF–2–A, Statement and Conduct Scoping at http://www.nrc.gov/reading-rm/ ‘‘Reactor Core Thermal-Hydraulics Process adams.html, which provides access through the NRC’s Electronic Reading Using the VIPRE–D Computer Code,’’ Exelon Nuclear Texas Holdings, LLC (3) Implementation of a Statistical Room (ERR) link. The accession number (Exelon) has submitted an application in ADAMS for the environmental report Design Limit for the analytic code and for an early site permit (ESP) for critical heat flux correlations that are is ML101120186. Persons who do not Victoria County Station (VCS) site, have access to ADAMS or who being used in DOM–NAF–2–A, and located approximately 13.3 miles south encounter problems in accessing the of the city of Victoria, Texas. The (4) Implementation of Dominion TR documents located in ADAMS should application for the ESP was submitted VEP–NE–2–A, ‘‘Statistical DNBR contact the NRC’s PDR Reference staff at by Exelon by letter dated March 25, Evaluation Methodology.’’ 1–800–397–4209/301–415–4737 or via 2010, pursuant to title 10 of the Code of The requested change also affects the e-mail to [email protected]. The Federal Regulations (10 CFR), parts 51 facility TSs. Items 1 and 2 in the above application may also be viewed on the list are methodologies that are used in and 52. A notice of receipt and availability of Internet at http://www.nrc.gov/reactors/ the determination of core operating new-reactors/esp/victoria.html. In limits; hence, items were put into the the application, including the environmental report (ER), was addition, the Victoria Public Library reference list contained in TS 6.2.C, located at 302 North Main Street in ‘‘CORE OPERATING LIMITS REPORT.’’ published in the Federal Register on Wednesday, April 28, 2010 (75 FR Victoria, Texas, has agreed to maintain Additional TS changes are being a copy of the ER and make it available implemented to provide consistency 22434). A notice of acceptance for docketing of the application for the ESP for public inspection. with the Improved TS format in NURG– The following key reference was published in the Federal Register 1431, Revision 3, ‘‘Standard Technical documents related to the application on June 14, 2010 (75 FR 33653). A Specifications, Westinghouse Plants,’’ and the NRC staff’s review processes are notice of hearing and opportunity to where practical, and to delete obsolete available through the NRC’s Web site at petition for leave to intervene in the TS requirements. http://www.nrc.gov: proceeding of the application will be Date of issuance: October 19, 2010. a. 10 CFR Part 51, Environmental published at a later date. Protection Regulations for Domestic Effective date: As of the date of The purposes of this notice are: (1) To Licensing and Related Regulatory issuance and shall be implemented inform the public that the U.S. Nuclear within 60 days. Function; Regulatory Commission (NRC) staff will b. 10 CFR Part 52, Licenses, Amendment Nos.: 270 and 269. be preparing an environmental impact Certifications, and Approvals for Renewed Facility Operating License statement (EIS) as part of the review of Nuclear Power Plants; Nos. DPR–32 and DPR–37: Amendments the application for the ESP and (2) to c. 10 CFR Part 100, Reactor Site changed the licenses and the technical provide the public with an opportunity Criteria; specifications. to participate in the environmental d. NUREG–1555, Standard Review Date of initial notice in Federal scoping process as defined in 10 CFR Plans for Environmental Reviews for Register: December 1, 2009 (74 FR 51.29. The NRC has invited the U.S. Nuclear Power Plants; 62838). The supplement provided Army Corps of Engineers, Galveston e. NUREG/BR–0298, Brochure on clarifying information that did not District, to participate in the preparation Nuclear Power Plant Licensing Process; change the scope of the original of the EIS as a cooperating agency. f. Regulatory Guide 4.2, Preparation of application and the initial proposed no In addition, as outlined in 36 CFR Environmental Reports for Nuclear ‘‘ significant hazards consideration 800.8(c), Coordination with the Power Stations; ’’ determination. National Environmental Policy Act, the g. Regulatory Guide 4.7, General Site NRC staff plans to coordinate Suitability Criteria for Nuclear Power The Commission’s related evaluation compliance with Section 106 of the of the amendments is contained in a Stations; National Historic Preservation Act h. Fact Sheet on Nuclear Power Plant Safety Evaluation dated October 19, (NHPA) with steps taken to meet the Licensing Process; 2010. requirements of the National i. Regulatory Guide 1.206, Combined No significant hazards consideration Environmental Policy Act of 1969, as License Applications for Nuclear Power comments received: No. amended (NEPA). Pursuant to 36 CFR Plants; and Dated at Rockville, Maryland, this 21st day 800.8(c), the NRC staff intends to use j. Nuclear Regulatory Commission of October 2010. the process and documentation for the Policy Statement on the Treatment of

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