Source: https://regulations.justia.com/regulations/fedreg/2011/07/05/2011-16275.html
Timestamp: 2020-01-27 18:47:28
Document Index: 311705928

Matched Legal Cases: ['art 50', 'art 50', 'art 50', 'art 50', 'art 50', 'art 51', 'art 2', 'art 2']

Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information, 39136-39141 [2011-16275] :: Nuclear Regulatory Commission :: Agencies And Commissions :: Regulation Tracker :: Justia
Justia Regulation Tracker Agencies And Commissions Nuclear Regulatory Commission Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information, 39136-39141 [2011-16275]
Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information, 39136-39141 [2011-16275]
Download as PDF 39136 Federal Register / Vol. 76, No. 128 / Tuesday, July 5, 2011 / Notices srobinson on DSK4SPTVN1PROD with NOTICES does not serve the underlying purpose of the regulations. Based on the above, the application of the subject record keeping requirements to the ZNPS’ records specified above is not required to achieve the underlying purpose of the rule. Thus, special circumstances are present which the NRC may consider, pursuant to 10 CFR 50.12(a)(2)(ii), to grant the requested exemption. 4.0 Conclusion Section 50.12 allows the Commission to grant specific exemptions to the record retention requirements specified in 10 CFR part 50 provided the requirements of 10 CFR 50.12 are satisfied. The staff has determined that the requested partial exemption from the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, Appendix A; 10 CFR part 50, Appendix B; and 10 CFR 50.59(d)(3) will not present an undue risk to the public health and safety. The destruction of the identified records will not impact remaining decommissioning activities; plant operations, configuration, and/or radiological effluents; operational and/ or installed SSCs that are quality-related or important to safety; or nuclear security. The staff has determined that the destruction of the identified records is administrative in nature and does not involve information or activities that could potentially impact the common defense and security of the United States. The staff has determined that the purpose for the record keeping regulations is to ensure that the licensing and design basis of the facility is understood, documented, preserved and retrievable relative to establishing and maintaining the SSC’s safety functions for the life of the facility. Since the ZNPS’ SSCs that were safetyrelated or important-to-safety will be removed from the licensing basis and removed from the plant, the staff agrees that the records identified in the partial exemption will no longer be required to achieve the underlying purpose of the rule. Therefore, the Commission grants ZionSolutions the requested partial exemption to the record keeping requirements of 10 CFR 50.71(c); 10 CFR part 50, Appendix A; 10 CFR part 50, Appendix B; and 10 CFR 50.59(d)(3), as described in the February 28, 2011, letter as supplemented on April 5, 2011. The Commission has determined that this licensing action meets the categorical exclusion provision in 10 CFR part 51.22(c)(25), as this action is VerDate Mar<15>2010 17:58 Jul 01, 2011 Jkt 223001 an exemption from the requirements of the Commission’s regulations, and (i) there is no significant hazards consideration; (ii) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (iii) there is no significant increase in individual or cumulative public or occupational radiation exposure; (iv) there is no significant construction impact; (v) there is no significant increase in the potential for or consequences from radiological accidents; and (vi) the requirements from which an exemption is sought involve recordkeeping requirements. Therefore, this action does not require either an environmental assessment or an environmental impact statement. This exemption is effective upon issuance. Dated at Rockville, Maryland, this 22nd day of June 2011. For the Nuclear Regulatory Commission. Keith I. McConnell, Deputy Director, Decommissioning and Uranium Recovery, Licensing Directorate, Division of Waste Management and Environmental Protection, Office of Federal and State Materials and Environmental Management Programs. [FR Doc. 2011–16723 Filed 7–1–11; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2011–0138] Applications and Amendments to Facility Operating Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information Nuclear Regulatory Commission. ACTION: Notice of license amendment request, opportunity to comment, opportunity to request a hearing. AGENCY: Comments must be filed by August 4, 2011. A request for a hearing must be filed by September 6, 2011. Any potential party as defined in Title 10 of the Code of Federal Regulations (10 CFR), 2.4 who believes access to Sensitive Unclassified Non-Safeguards Information (SUNSI) is necessary to respond to this notice must request document access by July 15, 2011. ADDRESSES: Please include Docket ID NRC–2011–0138 in the subject line of DATES: PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 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. 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 any one of the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC–2011–0138. Address questions about NRC dockets to Carol Gallagher, telephone: 301–492–3668; e-mail: Carol.Gallagher@nrc.gov. • Mail comments to: Cindy Bladey, 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, Room O1– 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 by e-mail to pdr.resource@nrc.gov. • Federal Rulemaking Web site: Public comments and supporting materials related to this notice can be found at http://www.regulations.gov by E:\FR\FM\05JYN1.SGM 05JYN1 Federal Register / Vol. 76, No. 128 / Tuesday, July 5, 2011 / Notices searching on Docket ID NRC–2011– 0138. srobinson on DSK4SPTVN1PROD with NOTICES Background Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (the Commission, NRC, or NRC staff) is publishing this notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to issue and make immediately effective any amendment to an operating license upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This notice includes notices of amendments containing SUNSI. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The Commission has made a proposed determination that the following amendment requests involve no significant hazards consideration. Under the Commission’s regulations in 10 CFR 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; (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. The basis for this proposed determination for each amendment request is shown below. 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 60day period provided that its final determination is that the 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 VerDate Mar<15>2010 17:58 Jul 01, 2011 Jkt 223001 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. 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 NRC’s PDR, located at One White Flint North, Room O1–F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The 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 petition for leave to intervene is filed within 60 days, 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 set forth the specific PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 39137 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 requestor/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 requestor/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 consideration. The contention must be one which, if proven, would entitle the requestor/ 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, and the Commission has not made a final determination on the issue of no significant hazards consideration, 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, then 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 E:\FR\FM\05JYN1.SGM 05JYN1 srobinson on DSK4SPTVN1PROD with NOTICES 39138 Federal Register / Vol. 76, No. 128 / Tuesday, July 5, 2011 / Notices 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 EFiling 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 10 days prior to the filing deadline, the participant should contact the Office of the Secretary by e-mail at hearing.docket@nrc.gov, or by telephone at 301–415–1677, to request (1) A digital identification (ID) certificate, which allows the participant (or its counsel or 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 counsel or representative, already holds an NRCissued digital ID 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 digital ID certificate is available on the NRC’s public Web site at http:// www.nrc.gov/site-help/e-submittals/ apply-certificates.html. System requirements for accessing the ESubmittal server are detailed in the NRC’s ‘‘Guidance for Electronic Submission,’’ which is available on the agency’s public Web site at http:// www.nrc.gov/site-help/esubmittals.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 Electronic Information Exchange System, 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, VerDate Mar<15>2010 17:58 Jul 01, 2011 Jkt 223001 is available on the NRC’s public Web site at http://www.nrc.gov/site-help/esubmittals.html. Once a participant has obtained a digital ID 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 the NRC guidance available on the NRC public Web site at http://www.nrc.gov/sitehelp/e-submittals.html. A filing 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 EFiling 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 email 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 counsel or representative) must apply for and receive a digital ID 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/esubmittals.html, by e-mail at MSHD.Resource@nrc.gov, or by a tollfree call at 1–866–672–7640. The NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern Time, Monday through Friday, excluding government holidays. Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, Attention: Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service to the Office of the Secretary, PO 00000 Frm 00071 Fmt 4703 Sfmt 4703 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 firstclass 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 the 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. Nontimely 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 amendment action, see the application for amendment which is available for public inspection at the NRC’s PDR, located at One White Flint North, Room O1–F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. 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. If you do not have access to ADAMS or if there are problems in accessing the documents located in ADAMS, contact the PDR Reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail to pdr.resource@nrc.gov. E:\FR\FM\05JYN1.SGM 05JYN1 Federal Register / Vol. 76, No. 128 / Tuesday, July 5, 2011 / Notices srobinson on DSK4SPTVN1PROD with NOTICES Dominion Nuclear Connecticut Inc., et al., Docket No. 50–423, Millstone Power Station, Unit 3, New London County, Connecticut Date of amendment request: January 20, 2011. Description of amendment request: This amendment request contains sensitive unclassified non-safeguards information (SUNSI). The amendment would revise the Millstone Power Station, Unit No. 3 (MPS3) Technical Specification (TS) 6.8.4.g, ‘‘Steam Generator (SG) Program,’’ to exclude a portion of the tubes below the top of the steam generator tubesheet from periodic steam generator tube inspections during Refueling Outage 14 and the subsequent operating cycle. The amendment request would also revise the reporting criteria in MPS3 TS 6.9.1.7, ‘‘Steam Generator Tube Inspection Report,’’ to remove reference to previous one-time alternate repair criteria and add reporting requirements specific to temporary alternate repair criteria. Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below, along with NRC edits noted in square brackets: (1) Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The previously analyzed accidents are initiated by the failure of plant structures, systems, or components. The proposed change that alters the steam generator inspection criteria and the steam generator inspection reporting criteria does not have a detrimental impact on the integrity of any plant structure, system, or component that initiates an analyzed event. The proposed change will not alter the operation of, or otherwise increase the failure probability of any plant equipment that initiates an analyzed accident. Of the applicable accidents previously evaluated, the limiting transients with consideration to the proposed change to the steam generator tube inspection and repair criteria are the steam generator tube rupture (SGTR) event and the feedline break (FLB) postulated accidents. During the SGTR event, the required structural integrity margins of the steam generator tubes and the tube-to-tubesheet joint over the H* distance will be maintained. Tube rupture in tubes with cracks within the tubesheet is precluded by the constraint provided by the tube-totubesheet joint. This constraint results from the hydraulic expansion process, thermal expansion mismatch between the tube and tubesheet, and from the differential pressure between the primary and secondary side. Based on this design, the structural margins VerDate Mar<15>2010 17:58 Jul 01, 2011 Jkt 223001 against burst, as discussed in Regulatory Guide (RG) 1.121, ‘‘Bases for Plugging Degraded PWR Steam Generator Tubes,’’ (Reference 25 [in the January 20, 2011, letter]) are maintained for both normal and postulated accident conditions. The proposed change has no impact on the structural or leakage integrity of the portion of the tube outside of the tubesheet. The proposed change maintains structural integrity of the steam generator tubes and does not affect other systems, structures, components, or operational features. Therefore, the proposed change results in no significant increase in the probability of the occurrence of a SGTR accident. At normal operating pressures, leakage from primary water stress corrosion cracking below the proposed limited inspection depth is limited by both the tube-to-tubesheet crevice and the limited crack opening permitted by the tubesheet constraint. Consequently, negligible normal operating leakage is expected from cracks within the tubesheet region. The consequences of an SGTR event are affected by the primary-tosecondary leakage flow during the event. However, primary-to-secondary leakage flow through a postulated broken tube is not affected by the proposed changes since the tubesheet enhances the tube integrity in the region of the hydraulic expansion by precluding tube deformation beyond its initial hydraulically expanded outside diameter. Therefore, the proposed changes do not result in a significant increase in the consequences of a SGTR. The consequences of a steam line break (SLB) are also not significantly affected by the proposed changes. During a SLB accident, the reduction in pressure above the tubesheet on the shell side of the steam generator creates an axially uniformly distributed load on the tubesheet due to the reactor coolant system pressure on the underside of the tubesheet. The resulting bending action constrains the tubes in the tubesheet thereby restricting primary-tosecondary leakage below the mid-plane. Primary-to-secondary leakage from tube degradation in the tubesheet area during the limiting accident (i.e., a SLB) is limited by flow restrictions. These restrictions result from the crack and tube-to-tubesheet contact pressures that provide a restricted leakage path above the indications and also limit the degree of potential crack face opening as compared to free span indications. The leakage factor of 2.49 for Millstone Power Station Unit 3 (MPS3), for a postulated SLB/FLB, has been calculated as shown in Table RA124–2 (Revised Table 9–7) of Reference 19 [in the January 20, 2011, letter]. Specifically, for the condition monitoring (CM) assessment, the component of leakage from the prior cycle from below the H* distance will be multiplied by a factor of 2.49 and added to the total leakage from any other source and compared to the allowable accident induced leakage limit. For the operational assessment (OA), the difference in the leakage between the allowable leakage and the accident induced leakage from sources other than the tubesheet expansion region will be divided by 2.49 and compared to the observed operational leakage. PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 39139 The probability of a SLB is unaffected by the potential failure of a steam generator tube as the failure of the tube is not an initiator for a SLB event. SLB leakage is limited by leakage flow restrictions resulting from the leakage path above potential cracks through the tube-to-tubesheet crevice. The leak rate during postulated accident conditions (including locked rotor) has been shown to remain within the accident analysis assumptions for all axial and or circumferentially orientated cracks occurring 15.2 inches below the top of the tubesheet. The accident induced leak rate limit is 1.0 gpm [gallon per minute]. The TS operational leak rate is 150 gpd [gallon per day] (0.1 gpm) through any one steam generator. Consequently, there is significant margin between accident leakage and allowable operational leakage. The SLB/FLB leak rate ratio is only 2.49 resulting in significant margin between the conservatively estimated accident leakage and the allowable accident leakage (1.0 gpm). Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. (2) Does the change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No The proposed change that alters the steam generator inspection criteria and the steam generator inspection reporting criteria does not introduce any new equipment, create new failure modes for existing equipment, or create any new limiting single failures. Plant operation will not be altered, and all safety functions will continue to perform as previously assumed in accident analyses. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. (3) Does the change involve a significant reduction in a margin of safety? Response: No. The proposed change that alters the steam generator inspection criteria and the steam generator inspection reporting criteria maintains the required structural margins of the steam generator tubes for both normal and accident conditions. NEI 97–06, Revision 2, ‘‘Steam Generator Program Guidelines’’ (Reference 1 [in the January 20, 2011, letter]) and RG 1.121, ‘‘Bases for Plugging Degraded PWR Steam Generator Tubes’’ (Reference 25 [in the January 20, 2011, letter]), are used as the bases in the development of the limited tubesheet [in the January 20, 2011, letter] inspection depth methodology for determining that steam generator tube integrity considerations are maintained within acceptable limits. RG 1.121 describes a method acceptable to the Nuclear Regulatory Commission for meeting GDC 14, ‘‘Reactor Coolant Pressure Boundary,’’ GDC 15, ‘‘Reactor Coolant System Design,’’ GDC 31, ‘‘Fracture Prevention of Reactor Coolant Pressure Boundary,’’ and GDC 32, ‘‘Inspection of Reactor Coolant Pressure Boundary,’’ by reducing the probability and consequences of a SGTR. This RG uses safety factors on loads for tube burst that are consistent with the requirements of Section E:\FR\FM\05JYN1.SGM 05JYN1 39140 Federal Register / Vol. 76, No. 128 / Tuesday, July 5, 2011 / Notices III of the American Society of Mechanical Engineers (ASME) Code. For axially oriented cracking located within the tubesheet, tube burst is precluded due to the presence of the tubesheet. For circumferentially oriented cracking, the H* analysis, documented in Section 4 of this license amendment request, defines the length of degradation-free, expanded tubing that provides the necessary resistance to tube pullout due to the pressure induced forces, with applicable safety factors applied. Application of the limited hot and cold leg tubesheet inspection criteria will preclude unacceptable primary-to-secondary leakage during all plant conditions. The methodology for determining leakage provides for large margins between calculated and actual leakage values in the proposed limited tubesheet inspection depth criteria. Therefore, the proposed change does not involve a significant reduction in any 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. Attorney for licensee: Lillian M. Cuoco, Senior Counsel, Dominion Resource Services, Inc., 120 Tredegar Street, RS–2, Richmond, VA 23219. NRC Branch Chief: Harold K. Chernoff. Order Imposing Procedures for Access to Sensitive Unclassified NonSafeguards Information for Contention Preparation srobinson on DSK4SPTVN1PROD with NOTICES Dominion Nuclear Connecticut Inc., et al., Docket No. 50–423, Millstone Power Station, Unit 3, New London County, Connecticut A. This Order contains instructions regarding how potential parties to this proceeding may request access to documents containing Sensitive Unclassified Non-Safeguards Information (SUNSI). B. Within 10 days after publication of this notice of hearing and opportunity to petition for leave to intervene, any potential party who believes access to SUNSI is necessary to respond to this notice may request such access. A ‘‘potential party’’ is any person who intends to participate as a party by demonstrating standing and filing an admissible contention under 10 CFR 2.309. Requests for access to SUNSI submitted later than 10 days after publication will not be considered absent a showing of good cause for the late filing, addressing why the request could not have been filed earlier. C. The requestor shall submit a letter requesting permission to access SUNSI VerDate Mar<15>2010 17:58 Jul 01, 2011 Jkt 223001 to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Attention: Rulemakings and Adjudications Staff, and provide a copy to the Associate General Counsel for Hearings, Enforcement and Administration, Office of the General Counsel, Washington, DC 20555–0001. The expedited delivery or courier mail address for both offices is: U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852. The e-mail address for the Office of the Secretary and the Office of the General Counsel are Hearing.Docket@nrc.gov and OGCmailcenter@nrc.gov, respectively.1 The request must include the following information: (1) A description of the licensing action with a citation to this Federal Register notice; (2) The name and address of the potential party and a description of the potential party’s particularized interest that could be harmed by the action identified in C.(1); (3) The identity of the individual or entity requesting access to SUNSI and the requestor’s basis for the need for the information in order to meaningfully participate in this adjudicatory proceeding. In particular, the request must explain why publicly-available versions of the information requested would not be sufficient to provide the basis and specificity for a proffered contention; D. Based on an evaluation of the information submitted under paragraph C.(3) the NRC staff will determine within 10 days of receipt of the request whether: (1) There is a reasonable basis to believe the petitioner is likely to establish standing to participate in this NRC proceeding; and (2) The requestor has established a legitimate need for access to SUNSI. E. If the NRC staff determines that the requestor satisfies both D.(1) and D.(2) above, the NRC staff will notify the requestor in writing that access to SUNSI has been granted. The written notification will contain instructions on how the requestor may obtain copies of the requested documents, and any other conditions that may apply to access to those documents. These conditions may include, but are not limited to, the signing of a Non-Disclosure Agreement or Affidavit, or Protective Order 2 setting forth terms and conditions to prevent the unauthorized or inadvertent disclosure of SUNSI by each individual who will be granted access to SUNSI. F. Filing of Contentions. Any contentions in these proceedings that are based upon the information received as a result of the request made for SUNSI must be filed by the requestor no later than 25 days after the requestor is granted access to that information. However, if more than 25 days remain between the date the petitioner is granted 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 contentions by that later deadline. G. Review of Denials of Access. (1) If the request for access to SUNSI is denied by the NRC staff either after a determination on standing and need for access, or after a determination on trustworthiness and reliability, the NRC staff shall immediately notify the requestor in writing, briefly stating the reason or reasons for the denial. (2) The requestor may challenge the NRC staff’s adverse determination by filing a challenge within 5 days of receipt of that determination with: (a) The presiding officer designated in this proceeding; (b) if no presiding officer has been appointed, the Chief Administrative Judge, or if he or she is unavailable, another administrative judge, or an administrative law judge with jurisdiction pursuant to 10 CFR 2.318(a); or (c) if another officer has been designated to rule on information access issues, with that officer. H. Review of Grants of Access. A party other than the requestor may challenge an NRC staff determination granting access to SUNSI whose release would harm that party’s interest independent of the proceeding. Such a challenge must be filed with the Chief Administrative Judge within 5 days of the notification by the NRC staff of its grant of access. If challenges to the NRC staff determinations are filed, these procedures give way to the normal process for litigating disputes concerning access to information. The availability of interlocutory review by the Commission of orders ruling on such NRC staff determinations (whether 1 While a request for hearing or petition to intervene in this proceeding must comply with the filing requirements of the NRC’s ‘‘E–Filing Rule,’’ the initial request to access SUNSI under these procedures should be submitted as described in this paragraph. 2 Any motion for Protective Order or draft NonDisclosure Affidavit or Agreement for SUNSI must be filed with the presiding officer or the Chief Administrative Judge if the presiding officer has not yet been designated, within 30 days of the deadline for the receipt of the written access request. PO 00000 Frm 00073 Fmt 4703 Sfmt 4703 E:\FR\FM\05JYN1.SGM 05JYN1 Federal Register / Vol. 76, No. 128 / Tuesday, July 5, 2011 / Notices granting or denying access) is governed by 10 CFR 2.311.3 I. The Commission expects that the NRC staff and presiding officers (and any other reviewing officers) will consider and resolve requests for access to SUNSI, and motions for protective orders, in a timely fashion in order to minimize any unnecessary delays in identifying those petitioners who have standing and who have propounded contentions meeting the specificity and basis requirements in 10 CFR part 2. Attachment 1 to this Order summarizes the general target schedule for processing and resolving requests under these procedures. It is so ordered. Dated at Rockville, Maryland, this 23rd day of June, 2011. 39141 For the Nuclear Regulatory Commission. Andrew L. Bates, Acting Secretary of the Commission. Attachment 1—General Target Schedule for Processing and Resolving Requests for Access to Sensitive Unclassified Non-Safeguards Information in This Proceeding Day Event/Activity 0 ........................................... Publication of Federal Register notice of hearing and opportunity to petition for leave to intervene, including order with instructions for access requests. Deadline for submitting requests for access to Sensitive Unclassified Non-Safeguards Information (SUNSI) with information: supporting the standing of a potential party identified by name and address; describing the need for the information in order for the potential party to participate meaningfully in an adjudicatory proceeding. Deadline for submitting petition for intervention containing: (i) Demonstration of standing; (ii) all contentions whose formulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 requestor/ petitioner reply). Nuclear Regulatory Commission (NRC) staff informs the requestor of the staff’s determination whether the request for access provides a reasonable basis to believe standing can be established and shows need for SUNSI. (NRC staff also informs any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information.) If NRC staff makes the finding of need for SUNSI and likelihood of standing, NRC staff begins document processing (preparation of redactions or review of redacted documents). If NRC staff finds no ‘‘need’’ or no likelihood of standing, the deadline for requestor/petitioner to file a motion seeking a ruling to reverse the NRC staff’s denial of access; NRC staff files copy of access determination with the presiding officer (or Chief Administrative Judge or other designated officer, as appropriate). If NRC staff finds ‘‘need’’ for SUNSI, the deadline for any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to file a motion seeking a ruling to reverse the NRC staff’s grant of access. Deadline for NRC staff reply to motions to reverse NRC staff determination(s). (Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for applicant/licensee to file Non-Disclosure Agreement for SUNSI. If access granted: Issuance of presiding officer or other designated officer decision on motion for protective order for access to sensitive information (including schedule for providing access and submission of contentions) or decision reversing a final adverse determination by the NRC staff. Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order. Deadline for submission of contentions whose development depends upon access to SUNSI. 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 contentions by that later deadline. (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI. (Answer receipt +7) Petitioner/Intervenor reply to answers. Decision on contention admission. 10 ......................................... 60 ......................................... 20 ......................................... 25 ......................................... 30 ......................................... 40 ......................................... A ........................................... A + 3 ..................................... A + 28 ................................... A + 53 ................................... A + 60 ................................... >A + 60 ................................ [FR Doc. 2011–16275 Filed 7–1–11; 8:45 am] BILLING CODE 7590–01–P POSTAL REGULATORY COMMISSION [Docket No. A2011–19; Order No. 754] Post Office Closing Postal Regulatory Commission. Notice. AGENCY: srobinson on DSK4SPTVN1PROD with NOTICES ACTION: This document informs the public that an appeal of the closing of the Lafayette Postal Facility has been filed. It identifies preliminary steps and provides a procedural schedule. SUMMARY: 3 Requestors should note that the filing requirements of the NRC’s E–Filing Rule (72 FR 49139; August 28, 2007) apply to appeals of NRC VerDate Mar<15>2010 17:58 Jul 01, 2011 Jkt 223001 Publication of this document will allow the Postal Service, petitioners, and others to take appropriate action. DATES: Administrative record due (from Postal Service): July 7, 2011; deadline for notices to intervene: July 25, 2011. See the Procedural Schedule in the SUPPLEMENTARY INFORMATION section for other dates of interest. ADDRESSES: Submit comments electronically by accessing the ‘‘Filing Online’’ link in the banner at the top of the Commission’s Web site (http:// www.prc.gov) or by directly accessing the Commission’s Filing Online system at https://www.prc.gov/prc-pages/filingonline/login.aspx. Commenters who cannot submit their views electronically should contact the person identified in the FOR FURTHER INFORMATION CONTACT section as the source for case-related information for advice on alternatives to electronic filing. staff determinations (because they must be served on a presiding officer or the Commission, as applicable), but not to the initial SUNSI request submitted to the NRC staff under these procedures. PO 00000 Frm 00074 Fmt 4703 Sfmt 4703 FOR FURTHER INFORMATION CONTACT: Stephen L. Sharfman, General Counsel, at 202–789–6820 (case-related information) or DocketAdmins@prc.gov (electronic filing assistance). Notice is hereby given that, pursuant to 39 U.S.C. 404(d), the Commission received two petitions for review of the closing of the Lafayette Postal Facility in Freehold, SUPPLEMENTARY INFORMATION: E:\FR\FM\05JYN1.SGM 05JYN1
[Pages 39136-39141]
[FR Doc No: 2011-16275]
[NRC-2011-0138]
DATES: Comments must be filed by August 4, 2011. A request for a
hearing must be filed by September 6, 2011. Any potential party as
defined in Title 10 of the Code of Federal Regulations (10 CFR), 2.4
document access by July 15, 2011.
ADDRESSES: Please include Docket ID NRC-2011-0138 in the subject line
2011-0138. Address questions about NRC dockets to Carol Gallagher,
supporting materials related to this notice can be found at http://www.regulations.gov by
searching on Docket ID NRC-2011-0138.
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
[[Page 39139]]
Power Station, Unit 3, New London County, Connecticut
amendment would revise the Millstone Power Station, Unit No. 3 (MPS3)
Technical Specification (TS) 6.8.4.g, ``Steam Generator (SG) Program,''
to exclude a portion of the tubes below the top of the steam generator
tubesheet from periodic steam generator tube inspections during
Refueling Outage 14 and the subsequent operating cycle. The amendment
request would also revise the reporting criteria in MPS3 TS 6.9.1.7,
previous one-time alternate repair criteria and add reporting
requirements specific to temporary alternate repair criteria.
consideration, which is presented below, along with NRC edits noted in
the operation of, or otherwise increase the failure probability of
any plant equipment that initiates an analyzed accident.
generator tube rupture (SGTR) event and the feedline break (FLB)
``Bases for Plugging Degraded PWR Steam Generator Tubes,''
(Reference 25 [in the January 20, 2011, letter]) are maintained for
both normal and postulated accident conditions.
by the primary-to-secondary leakage flow during the event. However,
primary-to-secondary leakage flow through a postulated broken tube
constrains the tubes in the tubesheet thereby restricting primary-
to-secondary leakage below the mid-plane.
The leakage factor of 2.49 for Millstone Power Station Unit 3
(MPS3), for a postulated SLB/FLB, has been calculated as shown in
Table RA124-2 (Revised Table 9-7) of Reference 19 [in the January
20, 2011, letter]. Specifically, for the condition monitoring (CM)
assessment, the component of leakage from the prior cycle from below
the H* distance will be multiplied by a factor of 2.49 and added to
the total leakage from any other source and compared to the
allowable accident induced leakage limit. For the operational
assessment (OA), the difference in the leakage between the allowable
leakage and the accident induced leakage from sources other than the
tubesheet expansion region will be divided by 2.49 and compared to
axial and or circumferentially orientated cracks occurring 15.2
inches below the top of the tubesheet. The accident induced leak
rate limit is 1.0 gpm [gallon per minute]. The TS operational leak
rate is 150 gpd [gallon per day] (0.1 gpm) through any one steam
generator. Consequently, there is significant margin between
accident leakage and allowable operational leakage. The SLB/FLB leak
rate ratio is only 2.49 resulting in significant margin between the
leakage (1.0 gpm).
criteria and the steam generator inspection reporting criteria does
not introduce any new equipment, create new failure modes for
existing equipment, or create any new limiting single failures.
Plant operation will not be altered, and all safety functions will
criteria and the steam generator inspection reporting criteria
2, ``Steam Generator Program Guidelines'' (Reference 1 [in the
January 20, 2011, letter]) and RG 1.121, ``Bases for Plugging
Degraded PWR Steam Generator Tubes'' (Reference 25 [in the January
20, 2011, letter]), are used as the bases in the development of the
limited tubesheet [in the January 20, 2011, letter] inspection depth
methodology for determining that steam generator tube integrity
describes a method acceptable to the Nuclear Regulatory Commission
consequences of a SGTR. This RG uses safety factors on loads for
tube burst that are consistent with the requirements of Section
[[Page 39140]]
III of the American Society of Mechanical Engineers (ASME) Code.
Section 4 of this license amendment request, defines the length of
degradation-free, expanded tubing that provides the necessary
[[Page 39141]]