Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process, 24126-24127 [E5-2208]

Download as PDF 24126 Federal Register / Vol. 70, No. 87 / Friday, May 6, 2005 / Notices consultation is required under section 106 of the National Historic Preservation Act. The NRC provided a draft of its Environmental Assessment (EA) to the following individuals: Mr. Dave Howland, Regional Engineer, Massachusetts Department of Environmental Protection, Western Regional Office, 436 Dwight Street, Springfield, MA 01103, Hartford, CT 06106–5127. Mr. Michael Whalen, Radiation Control Program, Massachusetts Department of Public Health, 90 Washington Street, Dorchester, MA 02121. Ms. Ruth McBurney, Texas Department of State Health Services, Radiation Control, 1100 West 49th Street, Austin, Texas 78756–3189. Ms. Susan Jablonski, Texas Commission on Environmental Quality, Mail Code 122, P.O. Box 13087, Austin, Texas 78711–3087. The Massachusetts Department of Environmental Protection stated the expectation that material leaving the YNPS site for disposal at WCS will be handled and transported consistent with all applicable Massachusetts Law and Regulation. The NRC staff also expects licensees to comply with all applicable transportation laws and regulations. The Texas Department of State Health Services (DSHS) provided several comments by letter dated March 24, 2005. In response to the DSHS comments, a statement was added to the Environmental Impacts of the Proposed Action section that this evaluation is for the disposal of the demolition debris at a subtitle C RCRA hazardous waste disposal facility irrespective of other materials disposed of at the facility. In addition, the Texas licensing authority over the WCS facility was clarified. DSHS also commented on the necessity of compliance with State regulatory requirements. The staff agrees with that comment and believes that the statement that, ‘‘any disposal must comply with State requirements,’’ adequately addresses that issue. The Texas Commission on Environmental Quality (TCEQ) provided comments by letter dated April 26, 2005. The primary focus of the TCEQ comments were on the Texas licensing requirements for the WCS facility and the authority for WCS to receive the radioactive material. This NRC action would permit Yankee to dispose of slightly contaminated demolition debris at the WCS facility, but does not authorize WCS to accept any material it is not otherwise licensed to receive under Texas licensing authority. As previously noted, ‘‘any disposal must comply with State requirements.’’ VerDate jul<14>2003 18:03 May 05, 2005 Jkt 205001 TCEQ also noted that only the bounding transportation option, truck shipment, was addressed in the draft EA. The EA has bee revised to address the rail shipment option as well. III. Finding of No Significant Impact On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action. Sources Used —U.S. NRC Power Reactor License: Yankee Atomic Electric Company Docket Number 050–00029, License Number DPR–03. —Yankee Atomic Electric Company, December 22, 2004, Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002 for alternate disposal at the Waste Control Specialist, LLC Facility in Andrews, Texas, (ML050110132) as supplemented on February 7, 2005. (ADAMS Accession Number ML050470301). —NRC 10 CFR 20.2002, ‘‘Method of Obtaining Approval of Proposed Disposal Procedures.’’ —NUREG–1640, ‘‘Radiological Assessment for Clearance of Materials from Nuclear Facilities.’’ —NUREG–1748, ‘‘Environmental Review Guidance for Licensing Actions Associated with NMSS Programs.’’ —U.S. DOT, Bureau of Transportation Statistics, ‘‘Transportation Statistics Annual Report,’’ September 2004. —U.S. DOT, Bureau of Transportation Statistics, ‘‘Freight Shipments in America,’’ April 2004. —NUREG–0586, Supplement 1, Generic Environmental Impact Statement of Decommissioning of Nuclear Facilities, November 2002. IV. Further Information For further details with respect to the proposed action, see the licensee’s letter dated December 22, 2004 (ADAMS Accession No. ML050110132), as supplemented on February 7, 2005 (ADAMS Accession No. ML050470301). The NRC Public Documents Room is located at NRC Headquarters in Rockville, MD, and can be contacted at (800) 397–4209. Documents may be examined, and/or copied for a fee, at the NRC’s Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from PO 00000 Frm 00166 Fmt 4703 Sfmt 4703 the Agencywide Documents Access and Management System’s (ADAMS) Public Library component on the NRC Web site, https://www.nrc.gov (the Public Electronic Reading Room). 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, or 301– 415–4737, or by e-mail at pdr@nrc.gov. Dated in Rockville, Maryland, this 28th day of April, 2005. For the Nuclear Regulatory Commission. Daniel M. Gillen, Deputy Director, Division of Waste Management and Environmental Protection, Office of Nuclear Material Safety and Safeguards. [FR Doc. E5–2206 Filed 5–5–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Notice of Availability of Model Application Concerning Technical Specification; Improvement To Modify Requirements Regarding Steam Generator Tube Integrity; Using the Consolidated Line Item Improvement Process Nuclear Regulatory Commission. ACTION: Notice of availability. AGENCY: SUMMARY: Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model application related to the revision of technical specifications (TS) on steam generator tube integrity for pressurized water reactors (PWRs). The purpose of this model is to permit the NRC to efficiently process amendments that propose to revise TS for steam generator tube integrity. Licensees of nuclear power reactors to which the model applies may request amendments utilizing the model application. DATES: The NRC staff issued a Federal Register notice (70 FR 10298, March 2, 2005) that provided a model safety evaluation (SE) and a model no significant hazards consideration (NSHC) determination relating to changing TS on steam generator tube integrity for PWRs. The NRC staff hereby announces that the model SE and NSHC determination may be referenced in plant-specific applications to adopt the changes. The staff has posted a model application on the NRC Web site to assist licensees in using the consolidated line item improvement process (CLIIP) to revise the TS on steam generator tube integrity. The NRC E:\FR\FM\06MYN1.SGM 06MYN1 Federal Register / Vol. 70, No. 87 / Friday, May 6, 2005 / Notices staff can most efficiently consider applications based upon the model application if the application is submitted within a year of this Federal Register notice. FOR FURTHER INFORMATION CONTACT: William Reckley, Mail Stop: O7D1, Division of Licensing Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, telephone 301–415–1323. SUPPLEMENTARY INFORMATION: Background Regulatory Issue Summary 2000–06, ‘‘Consolidated Line Item Improvement Process for Adopting Standard Technical Specification Changes for Power Reactors,’’ was issued on March 20, 2000. The CLIIP is intended to improve the efficiency of NRC licensing processes. This is accomplished by processing proposed changes to the standard TS (STS) in a manner that supports subsequent license amendment applications. The CLIIP includes an opportunity for the public to comment on proposed changes to the STS following a preliminary assessment by the NRC staff and finding that the change will likely be offered for adoption by licensees. The CLIIP directs the NRC staff to evaluate any comments received for a proposed change to the STS and to either reconsider the change or to proceed with announcing the availability of the change for proposed adoption by licensees. Those licensees opting to apply for the subject change to TS are responsible for reviewing the staff’s evaluation, referencing the applicable technical justifications, and providing any necessary plant-specific information. Each amendment application made in response to the notice of availability will be processed and noticed in accordance with applicable rules and NRC procedures. This notice involves the revision of limiting conditions for operation and related administrative controls in TS addressing steam generator tube integrity at PWRs. This proposed change was proposed for incorporation into the STS by participants in the Technical Specification Task Force (TSTF) and is designated TSTF–449, Revision 4. TSTF–449 can be viewed on the NRC Web site (https://www.nrc.gov). Applicability This proposed change to revise the TS on steam generator tube integrity is applicable to licensees for PWRs who have adopted or will adopt, in conjunction with the proposed change, technical specification requirements for VerDate jul<14>2003 18:03 May 05, 2005 Jkt 205001 a Bases control program consistent with the TS Bases Control Program described in Section 5.5 of the applicable vendor’s STS. To efficiently process the incoming license amendment applications, the staff requests each licensee applying for the changes addressed by TSTF–449 using the CLIIP to provide the information identified in the model application posted on the NRC Web site. 24127 Dated in Rockville, Maryland, this 2nd day of May 2005. For the Nuclear Regulatory Commission. Thomas H. Boyce, Section Chief, Technical Specifications Section, Operating Improvements Branch, Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation. [FR Doc. E5–2208 Filed 5–5–05; 8:45 am] BILLING CODE 7590–01–P Public Notices In a notice in the Federal Register dated March 2, 2005 (70 FR 10298), the staff requested comment on the use of the CLIIP to process requests to revise the TS regarding steam generator tube integrity. In addition, there have been several plant-specific amendment requests to adopt changes similar to those described in TSTF–449 and notices have been published for these applications. TSTF–449, as well as the NRC staff’s safety evaluation and model application, may be examined, and/or copied for a fee, at the NRC’s Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records are accessible electronically from the ADAMS Public Library component on the NRC Web site (the Electronic Reading Room). The staff received one response with comments following the notice published March 2, 2005 (70 FR 10298), soliciting comments on the model SE and NSHC determination related to TSTF–449, Revision 3. The comments were offered by the Nuclear Energy Institute (NEI) in a letter dated April 1, 2005. The NEI comments suggested clarifications and minor corrections to Revision 3 of TSTF–449 and related changes to the staff’s model SE. In response to comments, the TSTF submitted Revision 4 to TSTF–449 in its letter dated April 14, 2005. The NRC staff has made only minor changes to the model SE to address editorial issues and to reflect the revision of TSTF–449. The staff finds that the previously published models remain appropriate references (as modified slightly to reflect Revision 4 of TSTF–449) and has chosen not to republish the model SE and model NSHC determination in this notice. As described in the model application prepared by the staff, licensees may reference in their plantspecific applications to adopt TSTF– 449, the SE (as revised above), NSHC determination, and environmental assessment previously published in the Federal Register (70 FR 10298; March 2, 2005). PO 00000 Frm 00167 Fmt 4703 Sfmt 4703 OFFICE OF PERSONNEL MANAGEMENT Submission for OMB Review: Comment Request for Review of a Revised Information Collection: Procedures for Submitting Compensation and Leave Claims; OPM Form 1673 U.S. Office of Personnel Management. ACTION: Notice. AGENCY: SUMMARY: In accordance with the Paperwork Reduction Act of 1995 (Pub. L. 104–13, May 22, 1995), this notice announces that the U.S. Office of Personnel Management (OPM) submitted to the Office of Management and Budget (OMB) a request for review of a revised information collection. OPM Form 1673, Procedures for Submitting Compensation and Leave Claims, is used to collect information from current and former Federal civilian employees who are submitting a claim for compensation and/or leave. OPM needs this information in order to adjudicate the claim. We received no comments on our 60day notice on OPM Form 1673, published in the Federal Register on August 24, 2004. Approximately 40 claims are submitted annually. It takes approximately 60 minutes to complete the form. The annual estimated burden is 40 hours. For copies of this proposal, contact Mary Beth Smith-Toomey on (202) 606– 8358, Fax (202) 418–3251, or e-mail to mbtoomey@opm.gov. Please include a mailing address with your request. DATES: Comments on this proposal should be received within 30 calendar days from the date of this publication. ADDRESSES: Send or deliver comments to—Robert D. Hendler, Program Manager, Center for Merit Systems Compliance, Division for Human Capital Leadership and Merit System Compliance Group, U.S. Office of Personnel Management, 1900 E Street, NW., Room 6484, Washington, DC 20415; and Brenda Aguilar, OPM Desk E:\FR\FM\06MYN1.SGM 06MYN1

Agencies

[Federal Register Volume 70, Number 87 (Friday, May 6, 2005)]
[Notices]
[Pages 24126-24127]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-2208]


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NUCLEAR REGULATORY COMMISSION


Notice of Availability of Model Application Concerning Technical 
Specification; Improvement To Modify Requirements Regarding Steam 
Generator Tube Integrity; Using the Consolidated Line Item Improvement 
Process

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of availability.

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

SUMMARY: Notice is hereby given that the staff of the Nuclear 
Regulatory Commission (NRC) has prepared a model application related to 
the revision of technical specifications (TS) on steam generator tube 
integrity for pressurized water reactors (PWRs). The purpose of this 
model is to permit the NRC to efficiently process amendments that 
propose to revise TS for steam generator tube integrity. Licensees of 
nuclear power reactors to which the model applies may request 
amendments utilizing the model application.

DATES: The NRC staff issued a Federal Register notice (70 FR 10298, 
March 2, 2005) that provided a model safety evaluation (SE) and a model 
no significant hazards consideration (NSHC) determination relating to 
changing TS on steam generator tube integrity for PWRs. The NRC staff 
hereby announces that the model SE and NSHC determination may be 
referenced in plant-specific applications to adopt the changes. The 
staff has posted a model application on the NRC Web site to assist 
licensees in using the consolidated line item improvement process 
(CLIIP) to revise the TS on steam generator tube integrity. The NRC

[[Page 24127]]

staff can most efficiently consider applications based upon the model 
application if the application is submitted within a year of this 
Federal Register notice.

FOR FURTHER INFORMATION CONTACT: William Reckley, Mail Stop: O7D1, 
Division of Licensing Project Management, Office of Nuclear Reactor 
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone 301-415-1323.

SUPPLEMENTARY INFORMATION:

Background

    Regulatory Issue Summary 2000-06, ``Consolidated Line Item 
Improvement Process for Adopting Standard Technical Specification 
Changes for Power Reactors,'' was issued on March 20, 2000. The CLIIP 
is intended to improve the efficiency of NRC licensing processes. This 
is accomplished by processing proposed changes to the standard TS (STS) 
in a manner that supports subsequent license amendment applications. 
The CLIIP includes an opportunity for the public to comment on proposed 
changes to the STS following a preliminary assessment by the NRC staff 
and finding that the change will likely be offered for adoption by 
licensees. The CLIIP directs the NRC staff to evaluate any comments 
received for a proposed change to the STS and to either reconsider the 
change or to proceed with announcing the availability of the change for 
proposed adoption by licensees. Those licensees opting to apply for the 
subject change to TS are responsible for reviewing the staff's 
evaluation, referencing the applicable technical justifications, and 
providing any necessary plant-specific information. Each amendment 
application made in response to the notice of availability will be 
processed and noticed in accordance with applicable rules and NRC 
procedures.
    This notice involves the revision of limiting conditions for 
operation and related administrative controls in TS addressing steam 
generator tube integrity at PWRs. This proposed change was proposed for 
incorporation into the STS by participants in the Technical 
Specification Task Force (TSTF) and is designated TSTF-449, Revision 4. 
TSTF-449 can be viewed on the NRC Web site (https://www.nrc.gov).

Applicability

    This proposed change to revise the TS on steam generator tube 
integrity is applicable to licensees for PWRs who have adopted or will 
adopt, in conjunction with the proposed change, technical specification 
requirements for a Bases control program consistent with the TS Bases 
Control Program described in Section 5.5 of the applicable vendor's 
STS.
    To efficiently process the incoming license amendment applications, 
the staff requests each licensee applying for the changes addressed by 
TSTF-449 using the CLIIP to provide the information identified in the 
model application posted on the NRC Web site.

Public Notices

    In a notice in the Federal Register dated March 2, 2005 (70 FR 
10298), the staff requested comment on the use of the CLIIP to process 
requests to revise the TS regarding steam generator tube integrity. In 
addition, there have been several plant-specific amendment requests to 
adopt changes similar to those described in TSTF-449 and notices have 
been published for these applications.
    TSTF-449, as well as the NRC staff's safety evaluation and model 
application, may be examined, and/or copied for a fee, at the NRC's 
Public Document Room, located at One White Flint North, 11555 Rockville 
Pike (first floor), Rockville, Maryland. Publicly available records are 
accessible electronically from the ADAMS Public Library component on 
the NRC Web site (the Electronic Reading Room).
    The staff received one response with comments following the notice 
published March 2, 2005 (70 FR 10298), soliciting comments on the model 
SE and NSHC determination related to TSTF-449, Revision 3. The comments 
were offered by the Nuclear Energy Institute (NEI) in a letter dated 
April 1, 2005. The NEI comments suggested clarifications and minor 
corrections to Revision 3 of TSTF-449 and related changes to the 
staff's model SE. In response to comments, the TSTF submitted Revision 
4 to TSTF-449 in its letter dated April 14, 2005. The NRC staff has 
made only minor changes to the model SE to address editorial issues and 
to reflect the revision of TSTF-449. The staff finds that the 
previously published models remain appropriate references (as modified 
slightly to reflect Revision 4 of TSTF-449) and has chosen not to 
republish the model SE and model NSHC determination in this notice. As 
described in the model application prepared by the staff, licensees may 
reference in their plant-specific applications to adopt TSTF-449, the 
SE (as revised above), NSHC determination, and environmental assessment 
previously published in the Federal Register (70 FR 10298; March 2, 
2005).

    Dated in Rockville, Maryland, this 2nd day of May 2005.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Section Chief, Technical Specifications Section, Operating Improvements 
Branch, Division of Regulatory Improvement Programs, Office of Nuclear 
Reactor Regulation.
[FR Doc. E5-2208 Filed 5-5-05; 8:45 am]
BILLING CODE 7590-01-P
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