Source: https://regulations.justia.com/regulations/fedreg/2007/11/19/E7-22428.html
Timestamp: 2019-07-16 18:46:19
Document Index: 679677512

Matched Legal Cases: ['art 671', 'art 671', '§ 50', 'art 2', 'art 72', 'art 73']

Millstone Power Station, Unit No. 2; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing, 65084-65087 [E7-22428] :: Nuclear Regulatory Commission :: Agencies And Commissions :: Regulation Tracker :: Justia
Justia Regulation Tracker Agencies And Commissions Nuclear Regulatory Commission Millstone Power Station, Unit No. 2; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing, 65084-65087 [E7-22428]
Millstone Power Station, Unit No. 2; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing, 65084-65087 [E7-22428]
Download as PDF 65084 Federal Register / Vol. 72, No. 222 / Monday, November 19, 2007 / Notices and comparison group respondents over a three year period. Dated: November 13, 2007. Suzanne H. Plimpton, Reports Clearance Officer, National Science Foundation. [FR Doc. 07–5707 Filed 11–16–07; 8:45 am] BILLING CODE 7555–01–M NATIONAL SCIENCE FOUNDATION Notice of Permit Application Received Under the Antarctic Conservation Act of 1978 include requirements to report on the actual deployment of the Argo floats, in accordance with Antarctic waste regulations. Application for the permit is made by: Stephen C. Riser, School of Oceanography, University of Washington, Box 355350, Seattle, Washington 98195. Location: Wedell Sea and southern Indian Ocean. Dates: December 1, 2007 to February 28, 2008. AGENCY: Nadene G. Kennedy, Permit Officer. [FR Doc. E7–22504 Filed 11–16–07; 8:45 am] ACTION: BILLING CODE 7555–01–P rwilkins on PROD1PC63 with NOTICES National Science Foundation. Notice of Permit Applications Received Under the Antarctic Conservation Act. SUMMARY: Notice is hereby given that the National Science Foundation (NSF) has received a waste management permit application for deployment of approximately 30 Argo floats in the Weddell Sea and southern Indian Ocean, along cruise tracks of the German vessel POLARSTERN and the Norwegian vessel G.O. SARS during their voyages leaving from Cape Town early in 2008. The floats will drift freely at a depth of 1,000 or 2,000 meters for ten days, then ascent to the surface collecting temperature, salinity and pressure readings at 500–1000 depth. The profile data will be transmitted via Iridium satellite system. The floats are designed to last for about 200 cycles, or over 5 years. The application is submitted to NSF pursuant to regulations issued under the Antarctic Conservation Act of 1978. DATES: Interested parties are invited to submit written data, comments, or views with respect to this permit application by December 19, 2007. Permit applications may be inspected by interested parties at the Permit Office, address below. ADDRESSES: Comments should be addressed to Permit Office, Room 755, Office of Polar Programs, National Science Foundation, 4201 Wilson Boulevard, Arlington, Virginia 22230. FOR FURTHER INFORMATION CONTACT: Dr. Polly A. Penhale, Environmental Officer at the above address or (703) 292–8030. SUPPLEMENTARY INFORMATION: NSF’s Antarctic Waste Regulation, 45 CFR part 671, requires all U.S. citizens and entities to obtain a permit for the use or release of a designated pollutant in Antarctica, and for the release of waste in Antarctica. NSF has received a permit application under this Regulation for deployment of approximately 30 Argo floats. Conditions of the permit would VerDate Aug<31>2005 20:17 Nov 16, 2007 Jkt 214001 NATIONAL SCIENCE FOUNDATION Notice of Permit Application Received Under the Antarctic Conservation Act of 1978 National Science Foundation. Notice of permit applications received under the Antarctic Conservation Act. AGENCY: ACTION: Notice is hereby given that the National Science Foundation (NSF) has received a waste management permit application for a two-person kayaking team to establish camp sites while in the Antarctica Peninsula. The application is submitted to NSF pursuant to regulations issued under the Antarctic Conservation Act of 1978. DATES: Interested parties are invited to submit written data, comments, or views with respect to this permit application by December 19, 2007. Permit applications may be inspected by interested parties at the Permit Office, address below. ADDRESSES: Comments should be addressed to Permit Office, Room 755, Office of Polar Programs, National Science Foundation, 4201 Wilson Boulevard, Arlington, Virginia 22230. FOR FURTHER INFORMATION CONTACT: Dr. Polly A. Penhale, Environmental Officer at the above address or (703) 292–8030. SUPPLEMENTARY INFORMATION: NSF’s Antarctic Waste Regulation, 45 CFR part 671, requires all U.S. citizens and entities to obtain a permit for the use or release of a designated pollutant in Antarctica, and for the release of waste in Antarctica. NSF has received a permit application under this Regulation for some camping ashore will occur and any and all trash generated will be returned to the AUSTRALIS for disposal in accordance with the vessel’s permitted procedures. Fuel for cook stoves will be transferred to appropriate SUMMARY: PO 00000 Frm 00099 Fmt 4703 Sfmt 4703 fuel bottles prior to leaving South America. Any batteries taken ashore will be removed and non-rechargeable batteries will be returned to South America for disposal. Conditions of the permit would include requirements to report on the removal of materials and any accidental releases, and management of all waste, including human waste, in accordance with Antarctic waste regulations. Application for the permit is made by: Timothy J. Osse and Lisa A. Osse, 12415 68th Avenue, NE., Kirkland, Washington 98034. Location: Antarctic Peninsula. Dates: January 20, 2008 to February 8, 2008. Nadene G. Kennedy, Permit Officer. [FR Doc. E7–22514 Filed 11–16–07; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–336] Millstone Power Station, Unit No. 2; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission or NRC) is considering issuance of an amendment to Facility Operating License No. DPR–65 issued to Dominion Nuclear Connecticut (the licensee) for operation of the Millstone Power Station, Unit No. 2, located in New London County, Connecticut. The proposed amendment would revise Technical Specification (TS) 3/ 4.4.3, ‘‘Reactor Coolant System, Relief Valves’’ to modify the method of testing the pressurizer Power Operated Relief Valves (PORVs). Specifically, the requirement for bench testing the valves is changed to accommodate testing of the PORVs while installed in the plant. The change is requested due to the installation of new PORVs that are welded to the piping rather than bolted into the system. Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission’s regulations. The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission’s regulations in Title 10 E:\FR\FM\19NON1.SGM 19NON1 Federal Register / Vol. 72, No. 222 / Monday, November 19, 2007 / Notices rwilkins on PROD1PC63 with NOTICES of the Code of Federal Regulations (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; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed change does not modify any plant equipment and does not impact any failure modes that could lead to an accident. Additionally, the proposed change has no effect on the consequence of any analyzed accident since the change does not affect the function of any equipment credited for accident mitigation. In-situ testing versus bench testing does not decrease the reliability of the PORVs. Based on this discussion, the proposed amendment does not increase the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed change does not modify any plant equipment and there is no impact on the capability of existing equipment to perform its intended functions. No system setpoints are being modified and no changes are being made to the method in which plant operations are conducted. No new failure modes are introduced by the proposed change. The proposed amendment does not introduce accident initiators or malfunctions that would cause a new or different kind of accident. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The TS change does not involve a significant reduction in a margin of safety because the acceptance criterion (i.e., demonstration of function by operation of the PORV through one complete cycle of full travel at conditions representative of MODES 3 or 4) for the valve testing is the same. The proposed change does not affect any of the assumptions used in the accident analysis, nor does it affect any operability requirements for equipment important to plant safety. Therefore, the margin of safety is not impacted by the proposed amendment. The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three VerDate Aug<31>2005 20:17 Nov 16, 2007 Jkt 214001 standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 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 timely way would result, for example, in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently. Written comments may be submitted by mail to the Chief, Rulemaking, Directives and Editing Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Documents may be examined, and/or copied for a fee, at the NRC’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. The filing of requests for hearing and petitions for leave to intervene is discussed below. Within 60 days after the date of publication of this notice, the person(s) may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person(s) whose interest may be affected by this proceeding and who PO 00000 Frm 00100 Fmt 4703 Sfmt 4703 65085 wishes to participate as a party in the proceeding must file a written request via electronic submission through the NRC E-filing system for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission’s ‘‘Rules of Practice for Domestic Licensing Proceedings’’ in 10 CFR Part 2. Interested person(s) should consult a current copy of 10 CFR 2.309, which is available at the Commission’s PDR, located at One White Flint North, Public File Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management System’s (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/ reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order. As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements: (1) The name, address and telephone number of the requestor or petitioner; (2) the nature of the requestor’s/petitioner’s right under the Act to be made a party to the proceeding; (3) the nature and extent of the requestor’s/petitioner’s property, financial, or other interest in the proceeding; and (4) the possible effect of any decision or order which may be entered in the proceeding on the requestors/petitioner’s interest. The petition must also identify the specific contentions which the petitioner/ requestor 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 petitioner/requestor shall provide a brief explanation of the basis for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to E:\FR\FM\19NON1.SGM 19NON1 rwilkins on PROD1PC63 with NOTICES 65086 Federal Register / Vol. 72, No. 222 / Monday, November 19, 2007 / Notices rely in proving the contention at the hearing. The petitioner/requestor must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner/requestor who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing. If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment. Non-timely requests and/or petitions and contentions will not be entertained absent a determination by the Commission or the presiding officer of the Atomic Safety and Licensing Board that the petition, request and/or the contentions should be granted based on a balancing of the factors specified in 10 CFR 2.309(c)(1)(i) through (c)(1)(viii). A request for hearing or a petition for leave to intervene must be filed in accordance with the NRC E-Filing rule, which the NRC promulgated on August 28, 2007 (72 FR 49139). The E-Filing process requires participants to submit and serve 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 a waiver in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least five (5) VerDate Aug<31>2005 20:17 Nov 16, 2007 Jkt 214001 days prior to the filing deadline, the petitioner/requestor must contact the Office of the Secretary by e-mail at Hearingdocket@Nrc.Gov, or by calling (301) 415–1677, to request (1) a digital 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/or (2) creation of an electronic docket for the proceeding (even in instances in which the petitioner/requestor (or its counsel or representative) already holds an NRCissued digital ID certificate). Each petitioner/ requestor will need to download the Workplace Forms ViewerTM to access the Electronic Information Exchange (EIE), a component of the E-Filing system. The Workplace Forms ViewerTM is free and is available at http://www.nrc.gov/sitehelp/e-submittals/install-viewer.html. Information about applying for a digital ID certificate is available on NRC’s public Web site at http://www.nrc.gov/ site-help/e-submittals/applycertificates.html. Once a petitioner/requestor has obtained a digital ID certificate, had a docket created, and downloaded the EIE viewer, it can then submit a request for hearing or petition for leave to intervene. Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance available on the NRC public Web site at http://www.nrc.gov/site-help/esubmittals.html. A filing is considered complete at the time the filer submits its documents through EIE. To be timely, an electronic filing must be submitted to the EIE system no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt of the document. The EIE system also distributes an e-mail notice that provides access to the document to the NRC Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately. Therefore, applicants and other participants (or their 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 may seek assistance through the ‘‘Contact Us’’ link located on the NRC Web site at http://www.nrc.gov/site-help/e- PO 00000 Frm 00101 Fmt 4703 Sfmt 4703 submittals.html or by calling the NRC technical help line, which is available between 8:30 a.m. and 4:15 p.m., Eastern Time, Monday through Friday. The help line number is (800) 397–4209 or locally, (301) 415–4737. Participants who believe that they have a good cause for not submitting documents electronically must file a motion, 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, 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. Non-timely requests and/or petitions and contentions will not be entertained absent a determination by the Commission, the presiding officer, or the Atomic Safety and Licensing Board that the petition and/or request should be granted and/or the contentions should be admitted, based on a balancing of the factors specified in 10 CFR 2.309(c)(1)(i) through (c)(1)(viii). To be timely, filings must be submitted no later than 11:59 p.m. Eastern Time on the due date. Documents submitted in adjudicatory proceedings will appear in NRC’s electronic hearing docket which is available to the public at http:// www.nrc.gov/about-nrc/regulatory/ adjudicatory.html, unless excluded pursuant to an order of the Commission, an Atomic Safety and Licensing Board, or a 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. 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 submissions. For further details with respect to this license amendment application, see the E:\FR\FM\19NON1.SGM 19NON1 Federal Register / Vol. 72, No. 222 / Monday, November 19, 2007 / Notices application for amendment dated February 16, 2007, which is available for public inspection at the Commission’s PDR, located at One White Flint North, File Public Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management System’s (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http:// www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1–800– 397–4209, 301–415–4737, or by e-mail to pdr@nrc.gov. Federal Register to ensure that adequate notice has been given of an opportunity to request a hearing. The effective date of the Immediately Effective Order remains February 23, 2007, and its publication in the Federal Register does not impose any new or different requirements on the licensee. Requests for hearing from anyone other than the licensee must be filed within 20 days of the date of publication of this Notice in accordance with Section IV of the Immediately Effective Order. Pursuant to 10 CFR 2.202, NRC (or the Commission) is providing notice, in the matter of Three Mile Island Unit 2 (TMI–2) Independent Spent Fuel Storage Installation (ISFSI) Order Modifying License (Effective Immediately). For The Nuclear Regulatory Commission. John D. Hughey, Project Manager, Plant Licensing Branch 1– 2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E7–22428 Filed11–16–07; 8:45 am] II. Further Information BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 72–20; EA–06–298] In the Matter of Department of Energy—Idaho Operations Office; Three Mile Island Unit 2 Independent Spent Fuel Storage Installation Modifying License (Effective Immediately) U.S. Nuclear Regulatory Commission. ACTION: Issuance of Order Imposing Fingerprinting and Criminal History Check Requirements for Access to Safeguards Information. AGENCY: L. Raynard Wharton, Senior Project Manager, Licensing and Inspection Directorate, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards (NMSS), U.S. Nuclear Regulatory Commission (NRC), Washington, DC 20555–0001. Telephone: (301) 492– 3316; fax number: (301) 492–3348; email: lrw@nrc.gov. SUPPLEMENTARY INFORMATION: FOR FURTHER INFORMATION, CONTACT: rwilkins on PROD1PC63 with NOTICES I. Introduction The attached Immediately Effective Order was issued to the licensee on February 23, 2007. However, due to an administrative error, the Order was not published in the Federal Register at the time the Order was issued. Accordingly, this Order is now being published in the VerDate Aug<31>2005 20:17 Nov 16, 2007 Jkt 214001 I The NRC has issued a specific license, to the Department of Energy, Idaho Operations Office (DOE–ID), authorizing storage of spent fuel in an ISFSI in accordance with the Atomic Energy Act (AEA) of 1954, as amended, and Title 10 of the Code of Federal Regulations (10 CFR) part 72. On August 8, 2005, the Energy Policy Act of 2005 (EPAct) was enacted. Section 652 of the EPAct amended Section 149 of the AEA to require fingerprinting and a Federal Bureau of Investigation (FBI) identification and criminal history records check of any person who is to be permitted to have access to Safeguards Information (SGI).1 The NRC’s implementation of this requirement cannot await the completion of the SGI rulemaking, which is underway, because the EPAct fingerprinting and criminal history check requirements for access to SGI were immediately effective upon enactment of the EPAct. Although the EPAct permits the Commission by rule to except certain categories of individuals from the fingerprinting requirement, which the Commission has done [see 10 CFR 73.59, 71 FR 33989 (June 13, 2006)], it is unlikely that licensee employees are excepted from the fingerprinting requirement by the ‘‘fingerprinting relief’’ rule. Individuals relieved from fingerprinting and criminal history checks under the relief rule include Federal, State, and local officials and law enforcement personnel; Agreement State inspectors who conduct security inspections on behalf of the NRC; members of Congress 1 Safeguards Information is a form of sensitive, unclassified, security-related information that the Commission has the authority to designate and protect under Section 147 of the AEA. PO 00000 Frm 00102 Fmt 4703 Sfmt 4703 65087 and certain employees of members of Congress or Congressional Committees; and representatives of the International Atomic Energy Agency (IAEA) or certain foreign government organizations. In addition, individuals who have a favorably-decided U.S. Government criminal history check within the last five (5) years, and individuals who have active federal security clearances (provided in either case that they make available the appropriate documentation), have satisfied the EPAct fingerprinting requirement and need not be fingerprinted again. Therefore, in accordance with Section 149 of the AEA, as amended by the EPAct, the Commission is imposing additional requirements for access to SGI, as set forth by this Order, so that affected licensees can obtain and grant access to SGI.2 This Order also imposes requirements for access to SGI by any person,3 from any person, whether or not a Licensee, Applicant, or Certificate Holder of the Commission or Agreement States. II The Commission has broad statutory authority to protect and prohibit the unauthorized disclosure of SGI. Section 147 of the AEA grants the Commission explicit authority to issue such Orders as necessary to prohibit the unauthorized disclosure of SGI. Furthermore, Section 652 of the EPAct amended Section 149 of the AEA to require fingerprinting and an FBI identification and a criminal history records check of each individual who seeks access to SGI. In addition, no person may have access to SGI unless the person satisfies all other applicable requirements (e.g., 10 CFR 73.21). To provide assurance that appropriate measures are being implemented to comply with the fingerprinting and criminal history check requirements for 2 The storage and handling requirements for certain SGI have been modified from the existing 10 CFR part 73 SGI requirements that require a higher level of protection; such SGI is designated as Safeguards Information—Modified Handling (SGI–M). However, the information subject to the SGI–M handling and protection requirements is SGI, and licensees and other persons who seek or obtain access to such SGI are subject to this Order. 3 Person means (1) any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, government agency other than the Commission or the Department of Energy (DOE), except that the DOE shall be considered a person with respect to those facilities of the DOE specified in Section 202 of the Energy Reorganization Act of 1974 (88 Stat. 1244), any State or any political subdivision of, or any political entity within a State, any foreign government or nation or any political subdivision of any such government or nation, or other entity; and (2) any legal successor, representative, agent, or agency of the foregoing. E:\FR\FM\19NON1.SGM 19NON1
[Pages 65084-65087]
[FR Doc No: E7-22428]
Millstone Power Station, Unit No. 2; Notice of Consideration of
Significant Hazards Consideration Determination and Opportunity for a
DPR-65 issued to Dominion Nuclear Connecticut (the licensee) for
operation of the Millstone Power Station, Unit No. 2, located in New
London County, Connecticut.
The proposed amendment would revise Technical Specification (TS) 3/
4.4.3, ``Reactor Coolant System, Relief Valves'' to modify the method
of testing the pressurizer Power Operated Relief Valves (PORVs).
Specifically, the requirement for bench testing the valves is changed
to accommodate testing of the PORVs while installed in the plant. The
change is requested due to the installation of new PORVs that are
welded to the piping rather than bolted into the system.
[[Page 65085]]
The proposed change does not modify any plant equipment and does
not impact any failure modes that could lead to an accident.
Additionally, the proposed change has no effect on the consequence
of any analyzed accident since the change does not affect the
function of any equipment credited for accident mitigation. In-situ
testing versus bench testing does not decrease the reliability of
the PORVs. Based on this discussion, the proposed amendment does not
The proposed change does not modify any plant equipment and
there is no impact on the capability of existing equipment to
perform its intended functions. No system setpoints are being
modified and no changes are being made to the method in which plant
operations are conducted. No new failure modes are introduced by the
proposed change. The proposed amendment does not introduce accident
initiators or malfunctions that would cause a new or different kind
of accident. Therefore, the proposed amendment does not create the
The TS change does not involve a significant reduction in a
margin of safety because the acceptance criterion (i.e.,
demonstration of function by operation of the PORV through one
complete cycle of full travel at conditions representative of MODES
3 or 4) for the valve testing is the same. The proposed change does
not affect any of the assumptions used in the accident analysis, nor
does it affect any operability requirements for equipment important
to plant safety. Therefore, the margin of safety is not impacted by
[[Page 65086]]
2.309(c)(1)(i) through (c)(1)(viii). To be timely, filings must be
submitted no later than 11:59 p.m. Eastern Time on the due date.
http://www.nrc.gov/about-nrc/regulatory/adjudicatory.html, unless
numbers, home addresses, or home phone numbers in their filings. With
[[Page 65087]]
application for amendment dated February 16, 2007, which is available