Draft Regulatory Guide: Issuance, Availability, 74764-74765 [E8-29099]

Download as PDF 74764 Federal Register / Vol. 73, No. 237 / Tuesday, December 9, 2008 / Notices pwalker on PROD1PC71 with NOTICES part 20 for unrestricted release. The Licensee’s final status survey results were below these DCGLs and are in compliance with the As Low As Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The NRC thus finds that the Licensee’s final status survey results are acceptable. Based on its review, the staff has determined that the affected environment and any environmental impacts associated with the proposed action are bounded by the impacts evaluated by the ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities’’ (NUREG– 1496) Volumes 1–3 (ML042310492, ML042320379, and ML042330385). The staff finds there were no significant environmental impacts from the use of radioactive material at the Facility. The NRC staff reviewed the docket file records and the final status survey report to identify any non-radiological hazards that may have impacted the environment surrounding the Facility. No such hazards or impacts to the environment were identified. The NRC has identified no other radiological or non-radiological activities in the area that could result in cumulative environmental impacts. The NRC staff finds that the proposed release of the Facility for unrestricted use and the termination of the NRC materials license is in compliance with 10 CFR 20.1402. Based on its review, the staff considered the impact of the residual radioactivity at the Facility and concluded that the proposed action will not have a significant effect on the quality of the human environment. Environmental Impacts of the Alternatives to the Proposed Action Due to the largely administrative nature of the proposed action, its environmental impacts are small. Therefore, the only alternative the staff considered is the no-action alternative, under which the staff would leave things as they are by simply denying the amendment request. This no-action alternative is not feasible because it conflicts with 10 CFR 30.36(d), requiring that decommissioning of byproduct material facilities be completed and approved by the NRC after licensed activities cease. The NRC’s analysis of the Licensee’s final status survey data confirmed that the Facility meets the requirements of 10 CFR 20.1402 for unrestricted release and for license termination. Additionally, denying the amendment request would result in no change in current environmental impacts. The VerDate Aug<31>2005 17:00 Dec 08, 2008 Jkt 217001 environmental impacts of the proposed action and the no-action alternative are therefore similar, and the no-action alternative is accordingly not further considered. Conclusion The NRC staff has concluded that the proposed action is consistent with the NRC’s unrestricted release criteria specified in 10 CFR 20.1402. Because the proposed action will not significantly impact the quality of the human environment, the NRC staff concludes that the proposed action is the preferred alternative. Agencies and Persons Consulted NRC provided a draft of this Environmental Assessment to the State of Connecticut Department of Environmental Protection (DEP) for review on October 9, 2008. On November 6, 2008, DEP responded by email. The State agreed with the conclusions of the EA, and otherwise had no comments. The NRC staff has determined that the proposed action is of a procedural nature, and will not affect listed species or critical habitat. Therefore, no further consultation is required under Section 7 of the Endangered Species Act. The NRC staff has also determined that the proposed action is not the type of activity that has the potential to cause effects on historic properties. Therefore, no further consultation is required under Section 106 of the National Historic Preservation Act. III. Finding of No Significant Impact The NRC staff has prepared this EA in support of the proposed action. On the basis of this EA, the NRC finds that there are no significant environmental impacts from the proposed action, and that preparation of an environmental impact statement is not warranted. Accordingly, the NRC has determined that a Finding of No Significant Impact is appropriate. IV. Further Information Documents related to this action, including the application for license amendment and supporting documentation, are available electronically at the NRC(s Electronic Reading Room at http://www.nrc.gov/ reading-rm/adams.html. From this site, you can access the NRC’s Agencywide Document Access and Management System (ADAMS), which provides text and image files of NRC’s public documents. The documents related to this action are listed below, along with their ADAMS accession numbers. PO 00000 Frm 00082 Fmt 4703 Sfmt 4703 1. Letter dated September 1, 2008, with ‘‘Radiological Assessment Report, Neurogen Corporation, Northeast Industrial Road, Branford, CT 06504,’’ dated August 26, 2008; 2. NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance;’’ 3. Title 10, Code of Federal Regulations, Part 20, Subpart E, ‘‘Radiological Criteria for License Termination;’’ 4. Title 10, Code of Federal Regulations, Part 51, ‘‘Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions;’’ and 5. NUREG–1496, ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRCLicensed Nuclear Facilities.’’ If you do not have access to ADAMS, or if there are problems in accessing the documents located in ADAMS, contact the NRC Public Document Room (PDR) Reference staff at 1–800–397–4209, 301– 415–4737, or by e-mail to pdr@nrc.gov. These documents may also be viewed electronically on the public computers located at the NRC’s PDR, O 1 F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Dated at 475 Allendale Road, King of Prussia, Pennsylvania this 2nd day of December 2008. For the Nuclear Regulatory Commission. James Dwyer, Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I. [FR Doc. E8–29083 Filed 12–8–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Draft Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, DG–1203. FOR FURTHER INFORMATION CONTACT: Syed K. Shaukat, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Telephone: (301) 251– 7646; e-mail to Syed.Shaukat@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) has issued for public comment a draft guide in the agency’s ‘‘Regulatory Guide’’ series. This series E:\FR\FM\09DEN1.SGM 09DEN1 Federal Register / Vol. 73, No. 237 / Tuesday, December 9, 2008 / Notices pwalker on PROD1PC71 with NOTICES was developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC’s regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in its review of applications for permits and licenses. The draft regulatory guide, entitled, ‘‘Containment Performance for Pressure Loads,’’ is temporarily identified by its task number, DG–1203, which should be mentioned in all related correspondence. This guide describes methods that the staff of the NRC considers acceptable for demonstrating containment performance in nuclear power plants, in accordance with regulatory requirements and Commission’s performance goals for pressure loadings of containment structures. To meet these objectives, the NRC has developed formal regulatory requirements and has established several performance goals related to evaluating the maximum internal pressure capacity. II. Further Information The NRC staff is soliciting comments on DG–1203. Comments may be accompanied by relevant information or supporting data, and should mention DG–1203 in the subject line. Comments submitted in writing or in electronic form will be made available to the public in their entirety through the NRC’s Agencywide Documents Access and Management System (ADAMS). Personal information will not be removed from your comments. You may submit comments by any of the following methods: 1. Mail comments to: Rulemaking, Directives, and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. 2. E-mail comments to: nrcrep.resource@nrc.gov. 3. Hand-deliver comments to: Rulemaking, Directives, and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on Federal workdays. 4. Fax comments to: Rulemaking, Directives, and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 415–5144. Requests for technical information about DG–1203 may be directed to Syed K. Shaukat at (301) 251–7646 or by e-mail to Syed.Shaukat@nrc.gov. Comments would be most helpful if received by February 9, 2009. VerDate Aug<31>2005 17:00 Dec 08, 2008 Jkt 217001 Comments received after that date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before February 9, 2009. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time. Electronic copies of DG–1203 are available through the NRC’s public Web site under Draft Regulatory Guides in the ‘‘Regulatory Guides’’ collection of the NRC’s Electronic Reading Room at http://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also available in ADAMS (http:// www.nrc.gov/reading-rm/adams.html), under Accession No. ML082050539. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland. The PDR’s mailing address is USNRC PDR, Washington, DC 20555–0001. The PDR can also be reached by telephone at (301) 415–4737 or (800) 397–4205, by fax at (301) 415– 3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. Dated at Rockville, Maryland, this 1st day of December 2008. For the Nuclear Regulatory Commission. Andrea D. Valentin, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E8–29099 Filed 12–8–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Draft Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Draft Regulatory Guide (DG)–1189. FOR FURTHER INFORMATION CONTACT: John Voglewede, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, telephone: (301) 251–7555 or email to John.Voglewede@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) has issued for public comment a draft guide in the agency’s PO 00000 Frm 00083 Fmt 4703 Sfmt 4703 74765 Regulatory Guide Series. This series has been developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC’s regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in its review of applications for permits and licenses. The draft regulatory guide (DG), entitled, ‘‘An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification,’’ is temporarily identified by its task number, DG–1189, which should be mentioned in all related correspondence. DG–1189 is proposed Revision 2 of Regulatory Guide 1.126. This guide describes an analytical model and related assumptions and procedures that the staff of the NRC considers acceptable for predicting the effects of fuel densification in lightwater-cooled nuclear power reactors. To meet these objectives, the guide describes statistical methods related to product sampling that will ensure that this and other approved analytical models will adequately describe the effects of densification for each initial core and reload fuel quantity produced. II. Further Information The NRC staff is soliciting comments on DG–1189. Comments may be accompanied by relevant information or supporting data and should mention DG–1189 in the subject line. Comments submitted in writing or in electronic form will be made available to the public in their entirety through the NRC’s Agencywide Documents Access and Management System (ADAMS). Personal information will not be removed from your comments. You may submit comments by any of the following methods: 1. Mail comments to: Rulemaking, Directives, and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. 2. E-mail comments to: nrcrep.resource@nrc.gov. 3. Hand-deliver comments to: Rulemaking, Directives, and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission, 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. on Federal workdays. 4. Fax comments to: Rulemaking, Directives, and Editing Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 415–5144. Requests for technical information about DG–1189 may be directed to the E:\FR\FM\09DEN1.SGM 09DEN1

Agencies

[Federal Register Volume 73, Number 237 (Tuesday, December 9, 2008)]
[Notices]
[Pages 74764-74765]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-29099]


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NUCLEAR REGULATORY COMMISSION


Draft Regulatory Guide: Issuance, Availability

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, 
DG-1203.

-----------------------------------------------------------------------

FOR FURTHER INFORMATION CONTACT: Syed K. Shaukat, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, Telephone: (301) 251-
7646; e-mail to Syed.Shaukat@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC) has issued for public 
comment a draft guide in the agency's ``Regulatory Guide'' series. This 
series

[[Page 74765]]

was developed to describe and make available to the public such 
information as methods that are acceptable to the NRC staff for 
implementing specific parts of the NRC's regulations, techniques that 
the staff uses in evaluating specific problems or postulated accidents, 
and data that the staff needs in its review of applications for permits 
and licenses.
    The draft regulatory guide, entitled, ``Containment Performance for 
Pressure Loads,'' is temporarily identified by its task number, DG-
1203, which should be mentioned in all related correspondence. This 
guide describes methods that the staff of the NRC considers acceptable 
for demonstrating containment performance in nuclear power plants, in 
accordance with regulatory requirements and Commission's performance 
goals for pressure loadings of containment structures. To meet these 
objectives, the NRC has developed formal regulatory requirements and 
has established several performance goals related to evaluating the 
maximum internal pressure capacity.

II. Further Information

    The NRC staff is soliciting comments on DG-1203. Comments may be 
accompanied by relevant information or supporting data, and should 
mention DG-1203 in the subject line. Comments submitted in writing or 
in electronic form will be made available to the public in their 
entirety through the NRC's Agencywide Documents Access and Management 
System (ADAMS). Personal information will not be removed from your 
comments. You may submit comments by any of the following methods:
    1. Mail comments to: Rulemaking, Directives, and Editing Branch, 
Office of Administration, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001.
    2. E-mail comments to: nrcrep.resource@nrc.gov.
    3. Hand-deliver comments to: Rulemaking, Directives, and Editing 
Branch, Office of Administration, U.S. Nuclear Regulatory Commission, 
11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 
4:15 p.m. on Federal workdays.
    4. Fax comments to: Rulemaking, Directives, and Editing Branch, 
Office of Administration, U.S. Nuclear Regulatory Commission at (301) 
415-5144.
    Requests for technical information about DG-1203 may be directed to 
Syed K. Shaukat at (301) 251-7646 or by e-mail to Syed.Shaukat@nrc.gov.
    Comments would be most helpful if received by February 9, 2009. 
Comments received after that date will be considered if it is practical 
to do so, but the NRC is able to ensure consideration only for comments 
received on or before February 9, 2009. Although a time limit is given, 
comments and suggestions in connection with items for inclusion in 
guides currently being developed or improvements in all published 
guides are encouraged at any time.
    Electronic copies of DG-1203 are available through the NRC's public 
Web site under Draft Regulatory Guides in the ``Regulatory Guides'' 
collection of the NRC's Electronic Reading Room at http://www.nrc.gov/
reading-rm/doc-collections/. Electronic copies are also available in 
ADAMS (http://www.nrc.gov/reading-rm/adams.html), under Accession No. 
ML082050539.
    In addition, regulatory guides are available for inspection at the 
NRC's Public Document Room (PDR), which is located at 11555 Rockville 
Pike, Rockville, Maryland. The PDR's mailing address is USNRC PDR, 
Washington, DC 20555-0001. The PDR can also be reached by telephone at 
(301) 415-4737 or (800) 397-4205, by fax at (301) 415-3548, and by e-
mail to pdr.resource@nrc.gov.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

    Dated at Rockville, Maryland, this 1st day of December 2008.

    For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering, 
Office of Nuclear Regulatory Research.
[FR Doc. E8-29099 Filed 12-8-08; 8:45 am]
BILLING CODE 7590-01-P