Notices. Notice of availability
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BILLING CODE 7555-01-M NUCLEAR REGULATORY COMMISSION [Docket No. 50-199] Manhattan College; (Manhattan College Zero Power Reactor); Notice of Approval of Decommissioning Plan and Notice of License Termination The U.S. Nuclear Regulatory Commission
(NRC)is noticing the termination of Facility Operating License No. R-97 for the Manhattan College
(MC)Zero Power Reactor (MCZPR). The NRC has terminated the license of the decommissioned MCZPR, which was in the Leo Engineering Building of Manhattan College, Riverdale, New York, and has released the site for unrestricted use. The licensee requested termination of the license in a letter to NRC dated February 3, 2005. The MCZPR, a 0.1 watt swimming pool reactor, was constructed in 1964 and operated under License No. R-94. The reactor was permanently shut down in 1995. On March 23, 1999, NRC approved the decommissioning plan
(DP)dated July 21, 1998, by License Amendment No. 12. A Notice and Solicitation of Comments Pursuant to 10 CFR 20.1405 and 10 CFR 50.82(b)(5) Concerning Proposed Action to Decommission Manhattan College Zero Power Research Reactor appeared in the **Federal Register** on February 12, 1999 (64 FR 7214). The staff considered all comments received during the review of the MCZPR decommissioning plan. The NRC completed its review of the December 2004 final status survey report
(FSSR)for the Reactor Facility at Manhattan College School of Engineering. The licensee submitted the report to NRC by letter dated February 3, 2005. The report documented the level of residual radioactivity remaining at the facility and stated that compliance with the criteria as approved in the NRC-approved DP had been demonstrated. Pursuant to 10 CFR 50.82(b)(6), the NRC staff concluded that the decommissioning has been performed in accordance with the approved DP and that the final terminal radiation survey and associated documentation demonstrate that the facility and site are suitable for release in accordance with the criteria in the NRC-approved DP. Furthermore, on the basis of the decommissioning activities carried out by MC, the NRC's review of the licensee's FSSR, the results of NRC's inspections conducted at MC, and the results of NRC's confirmatory surveys, the NRC has concluded that the decommissioning process is complete and the facility and site are suitable to be released for unrestricted use. Based on the NRC staff's conclusions, Facility Operating License No. R-94 is terminated. For further details, see the licensee's application for decommissioning dated December 18, 1997, July 21, October 29, and November 10, 1998, and January 6, 1999; License Amendment No. 12 to Facility Operating License No. R-94; the licensee's February 3, 2005, request for license termination; the December 2004 FSSR for the Reactor Facility at the Manhattan College School of Engineering, submitted to NRC by letter dated February 3, 2005 and NRC Inspection Report 50-199/2005-201, dated July 15, 2005. Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records for MC dated after January 30, 2000, will be accessible electronically from the Agencywide Documents Access and Management System (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 have problems in accessing the documents in ADAMS should contact the NRC PDR reference staff at 1-800-397-4209 or 301-415-4737 or at *pdr@nrc.gov.* Dated at Rockville, Maryland, this 21st day of October 2005. For the Nuclear Regulatory Commission. Brian E. Thomas, Section Chief, Research and Test Reactors Section, New, Research and Test Reactors Program, Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation. [FR Doc. E5-5992 Filed 10-28-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [DOCKET NO. 030-34681] Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment for Morphochem, Inc.'s Facility in Monmouth Junction, NJ AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability. FOR FURTHER INFORMATION CONTACT: Betsy Ullrich, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania, 19406, telephone
(610)337-5040, fax
(610)337-5269; or by e-mail: *exu@nrc.gov.* SUPPLEMENTARY INFORMATION: I. Introduction The Nuclear Regulatory Commission
(NRC)is considering the issuance of a license amendment to Morphochem, Inc. for Materials License No. 29-30442-01, to authorize release of its facility in Monmouth Junction, New Jersey for unrestricted use. NRC has prepared an Environmental Assessment
(EA)in support of this action in accordance with the requirements of 10 CFR part 51. Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate. II. EA Summary The purpose of the action is to authorize the release of the licensee's Monmouth Junction, New Jersey facility for unrestricted use. Morphochem, Inc. was authorized by NRC from 1998 to use radioactive materials for research and development purposes at the site. On August 8, 2005, Morphochem, Inc. requested that NRC release the facility for unrestricted use. Morphochem, Inc. has conducted surveys of the facility and provided information to the NRC to demonstrate that the site meets the license termination criteria in Subpart E of 10 CFR part 20 for unrestricted use. The NRC staff has prepared an EA in support of the license amendment. The facility was remediated and surveyed prior to the licensee requesting the license amendment. The NRC staff has reviewed the information and final status survey submitted by Morphochem, Inc. Based on its review, the staff has determined that there are no additional remediation activities necessary to complete the proposed action. Therefore, the staff considered the impact of the residual radioactivity at the facility and concluded that since the residual radioactivity meets the requirements in Subpart E of 10 CFR part 20, a Finding of No Significant Impact is appropriate. III. Finding of No Significant Impact The staff has prepared the EA (summarized above) in support of the license amendment to terminate the license and release the facility for unrestricted use. The NRC staff has evaluated Morphochem, Inc.'s request and the results of the surveys and has concluded that the completed action complies with the criteria in Subpart E of 10 CFR part 20. The staff has found that the radiological environmental impacts from the action are bounded by the impacts evaluated by NUREG-1496, Volumes 1-3, “Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRC-Licensed Facilities” [ML042310492, ML042320379 and ML042330385]. Additionally, no non-radiological or cumulative impacts were identified. On the basis of the EA, the NRC has concluded that there are no significant environmental impacts from the proposed action and has determined not to prepare an environmental impact statement for the action. IV. Further Information Documents related to this action, including the application for the 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 ADAMS accession numbers for the documents related to this Notice are: “Environmental Assessment Related to an Amendment of U.S. Nuclear Regulatory Commission Materials License No. 29-30442-01, Issued to Morphochem, Inc.” [ML052940097]; and “Termination of NRC License Number 29-30442-01” dated August 8, 2005 [ML052270172]. 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
(800)397-4209 or
(301)415-4737, or by e-mail to *pdr@nrc.gov.* Documents related to operations conducted under this license not specifically referenced in this Notice may not be electronically available and/or may not be publicly available. Persons who have an interest in reviewing these documents should submit a request to NRC under the Freedom of Information Act (FOIA). Instructions for submitting a FOIA request can be found on the NRC's Web site at *http://www.nrc.gov/reading-rm/foia/foia-privacy.html.* Dated at King of Prussia, Pennsylvania, this 21st day of October, 2005. For the Nuclear Regulatory Commission. James P. Dwyer, Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety, Region I. [FR Doc. E5-5994 Filed 10-28-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Notice of Public Workshop on Draft Report for Comment: “Estimating Loss-of-Coolant Accident
(LOCA)Frequencies Through the Elicitation Process,” NUREG-1829 AGENCY: Nuclear Regulatory Commission. ACTION: Announcement of public workshop. Revision of workshop date. DATES: Workshop date, November 9, 2005. *Background:* The Nuclear Regulatory Commission
(NRC)issued draft NUREG-1829, “Estimating Loss-of-Coolant Accident
(LOCA)Frequencies Through the Elicitation Process,” for public comment in June 2005. The report is available under ADAMS Accession Number ML051520574 and on the NRC Web site at *http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1829/.* A separate notice was published in the **Federal Register** on October 4, 2005, announcing the availability of this report (70 FR 57901). This report describes LOCA frequency estimates developed using an expert elicitation process in support of an effort to develop a risk-informed revision of the emergency core cooling system
(ECCS)requirements for commercial nuclear power plants by redefinition of the design-basis break size. The expert elicitation process consolidates service history data and insights from probabilistic fracture mechanics
(PFM)studies with knowledge of plant design, operation, and material performance to arrive at the LOCA frequency estimates. The ECCS requirements in the United States are contained in 10 CFR 50.46, Appendix K to part 50, and General Design Criterion
(GDC)35. Specifically, ECCS design, reliability, and operating requirements exist to ensure that the system can successfully mitigate postulated LOCAs. Consideration of an instantaneous break with a flow rate equivalent to a double-ended guillotine break
(DEGB)of the largest pipe in the primary piping system of the plant generally provides the limiting condition in the required 10 CFR part 50, Appendix K analysis. However, the DEGB is widely recognized as an extremely unlikely event, so NRC staff is performing a risk-informed revision of the design-basis break size requirements. A central consideration in selecting a risk-informed design basis break size is an evaluation of the LOCA frequency as a function of break size. The most recent NRC-sponsored study of pipe break failure frequencies is contained in NUREG/CR-5750 (Poloski, 1999). Unfortunately, these estimates are not sufficient for design basis break size selection because they do not address all current passive-system degradation concerns (e.g., primary water stress corrosion cracking) and they do not discriminate among breaks having effective diameters greater than 6 inches. There have been two approaches traditionally used to estimate LOCA frequencies and their relationship to pipe size:
(i)Estimates based on statistical analysis of service experience data, and
(ii)PFM analysis of specific postulated failure mechanisms. Neither approach is fully suitable for evaluating LOCA event frequencies due to the rarity of these events and the modeling complexity. This study used an expert elicitation process, which is well-recognized for quantifying phenomenological knowledge when data or modeling approaches are insufficient. Elicitation responses from a panel of 12 experts determined individual LOCA frequency estimates for the 5th percentile, median, mean and 95th percentile of the frequency distribution for each of six LOCA categories. Group estimates were determined by aggregating the individual estimates using the geometric mean of the individual estimates for each frequency parameter (i.e., median, mean, 5th and 95th percentiles). Group variability was estimated by calculating 95% confidence bounds for each of the group frequency parameters. A number of sensitivity analyses were conducted to examine the effects on the quantitative results from variation of the assumptions, structure and techniques of the baseline analysis procedure. *Public Workshop:* The NRC will conduct a public workshop on Wednesday, November 9, 2005, to be held in room O6B4 at NRC Headquarters, 11545 Rockville Pike, Rockville, Maryland. This is a revision to the October 31, 2005, workshop date announced in the **Federal Register** Notice published, October 4, 2005; 70 FR 57901. The purpose of the workshop is to facilitate the comment process. In the workshop, the staff will provide an overview of the report and address clarification of items identified by the public. A preliminary agenda is attached. Persons planning to attend this meeting are urged to contact the below named individual at least two working days prior to the meeting to be advised of any potential changes to the agenda. The NRC seeks comments on the report and is especially interested in comments on the following questions: 1. Is the structure of the expert elicitation process appropriate for the stated problem and goals of the study? 2. Are the assumptions and methodology of the analysis framework used to process the panel responses appropriate and reasonable? Are they consistent with the type of information provided by the expert panel and the goals of the study? 3. Is the geometric mean aggregation methodology appropriate for the panel responses and the study goals? Should other aggregation methodologies be considered and what are their advantages and disadvantages? As previously published in the **Federal Register** , October 4, 2005; 70 FR 57901, the NRC will consider all written comments on draft NUREG-1829, “Estimating Loss-of-Coolant Accident
(LOCA)Frequencies Through the Elicitation Process,” received before November 30, 2005. Comments received after November 30, 2005, will be considered if time permits. Comments should be addressed to the contact listed below. An electronic version of the report and the accompanying experts' raw data files, are available electronically at *http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1829/* and through the NRC's Electronic Reading Room at *http://www.nrc.gov/reading-rm/adams.html.* From the latter 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 ADAMS accession numbers for the documents related to this notice are: Document title ADAMS Accession No. File format NUREG-1829 ML051520574 Adobe Acrobat Document. BWR Non-piping Raw Data for NUREG-1829 ML051580341 Adobe Acrobat Document. BWR Piping Raw Data for NUREG-1829 ML051580344 Adobe Acrobat Document. PWR Non-piping Raw Data for NUREG-1829 ML051580346 Adobe Acrobat Document. PWR Piping Raw Data for NUREG-1829 ML051580347 Adobe Acrobat Document. 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, O1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. FOR FURTHER INFORMATION CONTACT: Dr. Charles A. Greene, Mail Stop T10E10, U.S. Nuclear Regulatory Commission, 11545 Rockville Pike, Rockville, MD 20852, telephone
(301)415-6177, facsimile number:
(301)415-5074, e-mail *cag2@nrc.gov.* Dated at Rockville, Maryland, this 25th day of October 2005. For the Nuclear Regulatory Commission. Jennifer Uhle, Chief, Materials Engineering Branch, Division of Engineering Technology, Office of Nuclear Regulatory Research. Attachment—Preliminary Agenda Public Workshop on Draft Report for Comment: “Estimating Loss-of-Coolant Accident
(LOCA)Frequencies through the Elicitation Process,” NUREG-1829 November 9, 2005*—9 a.m.-12 p.m., Room O-4B6 Preliminary Agenda 9 a.m.-9:15 a.m.—Introduction 9:15 a.m.-9:45 a.m.—Overview of NUREG-1829 9:45 a.m.-10:15 a.m.—Clarification of items identified by the public 10:15 a.m.-10:30 a.m.—Break 10:30 a.m.-12 noon—Clarification of items identified by the audience 12 noon—Adjourn *Revised date [FR Doc. 05-21650 Filed 10-28-05; 8:45 am]
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