NUREG-1482, Revision 2, “Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment”, 52355-52356 [2011-21357]

Download as PDF Federal Register / Vol. 76, No. 162 / Monday, August 22, 2011 / Notices directed by the Antarctic Conservation Act of 1978 (Pub. L. 95–541), as amended by the Antarctic Science, Tourism and Conservation Act of 1996, has developed regulations for the establishment of a permit system for various activities in Antarctica and designation of certain animals and certain geographic areas a requiring special protection. The regulations establish such a permit system to designate Antarctic Specially Protected Areas. The applications received are as follows: Permit Application: 2012–006 1. Applicant: Jeff Bowman, University of Washington, Box 357940, Seattle, WA 98105–7940. Activity for Which Permit Is Requested Enter an Antarctic Specially Protected Area. The applicant plans to enter the Antarctic Specially Protect Area at Cape Royds, Ross Island (ASPA 121) to collect sea ice and seawater for microbial analysis. Location ASPA 121—Cape Royds, Ross island. Dates August 27, 2011 to November 2, 2011. Nadene G. Kennedy, Permit Officer, Office of Polar Programs. [FR Doc. 2011–21296 Filed 8–19–11; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [NRC–2010–0278] NUREG–1482, Revision 2, ‘‘Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment’’ Nuclear Regulatory Commission. ACTION: Announcement of issuance for public comment, availability. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) has issued for public comment a document entitled: NUREG– 1482, Revision 2, ‘‘Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment,’’ and subtitled ‘‘Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants’’. (Note that this document was submitted previously for public comments as draft NUREG–1946. Based on public comments, draft NUREG– 1482 is being updated as Revision 2 and jlentini on DSK4TPTVN1PROD with NOTICES SUMMARY: VerDate Mar<15>2010 17:16 Aug 19, 2011 Jkt 223001 is being issued to incorporate all comments received for draft report NUREG–1946). DATES: Please submit comments by December 20, 2011. Comments received after this date will be considered if it is practical to do so, but the NRC staff is able to ensure consideration only for comments received on or before this date. Please include Docket ID NRC–2010–0278 in the subject line of your comments. For additional instructions on submitting comments and instructions on accessing documents related to this action, see ‘‘Submitting Comments and Accessing Information’’ in the SUPPLEMENTARY INFORMATION section of this document. 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–2010–0278. 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. SUPPLEMENTARY INFORMATION: ADDRESSES: Submitting Comments and Accessing Information 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 can access publicly available documents related to this document using the following methods: • NRC’s Public Document Room (PDR): The public may examine and have copied, for a fee, publicly available PO 00000 Frm 00053 Fmt 4703 Sfmt 4703 52355 documents at the NRC’s PDR, 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. The NUREG– 1482, Revision 2, ‘‘Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment,’’ and subtitled ‘‘Inservice Testing of Pumps and Valves, and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants’’ is available electronically under ADAMS Accession Number ML112231412. • Federal Rulemaking Web Site: Public comments and supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID NRC–2010– 0278. FOR FURTHER INFORMATION CONTACT: Gurjendra S. Bedi, Division of Component Integrity, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: 301–415– 1393, e-mail: Gurjendra.Bedi@nrc.gov. NUREG–1482, Revision 2, ‘‘Guidelines for Inservice Testing at Nuclear Power Plants, Draft Report for Comment’’ provides updated information on applicable regulations for testing of pumps and valves, and inservice examination and testing of snubbers. The information in NUREG– 1482, ‘‘Guidelines for Inservice Testing at Nuclear Plants,’’ Revision 0, issued April 1995, and Revision 1, issued January 2005, has described these topics in the past. This NUREG report replaces Revision 0 and Revision 1 of NUREG–1482, and is applicable, unless stated otherwise, to all editions and addenda of the American Society of Mechanical Engineers (ASME) Code of Operation and Maintenance of Nuclear Power Plants (OM Code), which Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b) incorporates by reference (76 FR 36232–36279), dated June 21, 2011. Note that the draft NUREG–1482, Revision 2, is a substantial re-write from issuance of draft NUREG–1946 (ADAMS E:\FR\FM\22AUN1.SGM 22AUN1 52356 Federal Register / Vol. 76, No. 162 / Monday, August 22, 2011 / Notices Accession Number: ML102100236). This draft NUREG–1482, Revision 2, incorporates all the public comments received for draft NUREG–1946, because based on public comments, NUREG– 1482, Revision 1, is revised and updated instead of issuing the new NUREG– 1946. The NRC staff evaluation and resolution of public comments for draft NUREG–1946, including Inservice Testing Owner Group comments, are documented in ADAMS Accession Number: ML112092872. Most of the draft NUREG–1946 included in the main text of draft NUREG–1482, Revision 2, Appendix A, to this NUREG–1482, Revision 2, contains guidance provided in Revision 1 to NUREG–1482 for pumps and valves that has been updated for the development of inservice testing programs at nuclear power plants. Appendix B to this NUREG contains guidance related to inservice examination and testing of dynamic restraints (snubbers), which is included for the first time in the draft NUREG–1482, Revision 2. The guidelines and recommendations provided in this NUREG and its Appendices A and B do not supersede the regulatory requirements specified in 10 CFR 50.55a. Further, this NUREG does not authorize the use of alternatives to, or grant relief from, the ASME Code requirements for inservice testing of pumps and valves, or inservice examination and testing of dynamic restraints (snubbers), incorporated by reference in 10 CFR 50.55a. In addition, the NUREG discusses other inservice test program topics such as the NRC process for review of the OM Code, conditions on the use of the OM Code, and interpretations of the OM Code. Dated at Rockville, Maryland, this 11th day of August 2011. For the Nuclear Regulatory Commission. Anthony C. McMurtray, Chief, Component Performance and Testing Branch, Division of Component Integrity, Office of Nuclear Reactor Regulation. [FR Doc. 2011–21357 Filed 8–19–11; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION jlentini on DSK4TPTVN1PROD with NOTICES [NRC–2011–0188; Docket No. 50–315] Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, Unit 1; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an exemption VerDate Mar<15>2010 17:16 Aug 19, 2011 Jkt 223001 and an amendment to Renewed Facility Operating License No. NPF–58 issued to Indiana Michigan Power Company (the licensee), for operation of Donald C. Cook Nuclear Plant, Unit 1 (DCCNP–1), located in Berrien County, Michigan, in accordance with Title 10 of the Code of Federal Regulations (10 CFR) part 50, § 50.90. In accordance with 10 CFR 51.21, the NRC performed an environmental assessment documenting its findings. The NRC concluded that the proposed actions would have no significant environmental impact. Environmental Assessment Identification of the Proposed Actions The proposed actions would issue an exemption from 10 CFR 50.46 regarding fuel cladding material, and revise the Technical Specifications document, which is part of the Renewed Facility Operating Licenses, to permit use of Optimized ZIRLOTM fuel to a peak road average burnup limit of 62 gigawattdays per metric ton uranium (GWD/ MTU). The proposed actions are in accordance with the licensee’s application dated December 16, 2010. The Need for the Proposed Actions The proposed actions to issue an exemption to the fuel cladding requirement of 10 CFR 50.46, and to amend the Technical Specifications to permit use of Optimized ZIRLOTM fuel to a peak rod average burnup limit of 62 GWD/MTU would allow for more effective fuel management. If the exemption and amendment are not approved, the licensee will not be provided the opportunity to use Optimized ZIRLOTM fuel design with a peak rod average burnup as high as 62 GWD/MTU; the licensee would thus lose fuel management flexibility. Environmental Impacts of the Proposed Actions In this environmental assessment regarding the impacts of the use of Optimized ZIRLOTM fuel with the possible burnup up to 62 GWD/MTU, the Commission is relying on the results of the updated study conducted for the NRC by the Pacific Northwest National Laboratory (PNNL), entitled ‘‘Environmental Effects of Extending Fuel Burnup Above 60 GWD/MTU’’ (NUREG/CR–6703, PNNL–13257, January 2001). Environmental impacts of high burnup fuel up to 75 GWD/MTU were evaluated in the study, but some aspects of the review were limited to evaluating the impacts of the extended burnup up to 62 GWD/MTU, because of the need for additional data on the effect PO 00000 Frm 00054 Fmt 4703 Sfmt 4703 of extended burnup on gap release fractions. All the aspects of the fuelcycle were considered during the study, from mining, milling, conversion, enrichment and fabrication through normal reactor operation, transportation, waste management, and storage of spent fuel. The amendment and exemption would allow DCCNP–1 to use Optimized ZIRLOTM fuel up to a burnup limit of 62 GWD/MTU. The NRC staff has completed its evaluation of the proposed actions and concludes that such changes would not adversely affect plant safety, and would have no adverse effect on the probability of any accident. For the accidents that involve damage or melting of the fuel in the reactor core, fuel rod integrity has been shown to be unaffected by extended burnup under consideration; therefore, the probability of an accident will not be affected by fuel burnup to 62 GWD/MTU. For the accidents in which the reactor core remains intact, the increased burnup may slightly change the mix of fission products that could be released in the event of a serious accident, but because the radionuclides contributing most to the dose are short-lived, increased burnup would not have an effect on the consequences of a serious accident beyond the consequences of previously evaluated accident scenarios. Thus, there will be no significant increase in projected dose consequences of postulated accidents associated with fuel burnup up to 62 GWD/MTU, and doses will remain well below regulatory limits. Regulatory limits on radiological effluent releases are independent of burnup. The requirements of 10 CFR part 20, 10 CFR 50.36a, and Appendix I to 10 CFR part 50 ensure that routine releases of gaseous, liquid or solid radiological effluents to unrestricted areas is kept ‘‘As Low As is Reasonably Achievable.’’ Therefore, the NRC staff concludes that during routine operations, there would be no significant increase in the amount of gaseous radiological effluents released into the environment as a result of the proposed actions, nor will there be a significant increase in the amount of liquid radiological effluents or solid radiological effluents released into the environment. The proposed actions will not change normal plant operating conditions (i.e., no changes are expected in the fuel handling, operational, or storing processes). The fuel storage and handling, radioactive waste, and other systems which may contain radioactivity are designed to assure adequate safety under normal E:\FR\FM\22AUN1.SGM 22AUN1

Agencies

[Federal Register Volume 76, Number 162 (Monday, August 22, 2011)]
[Notices]
[Pages 52355-52356]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-21357]


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NUCLEAR REGULATORY COMMISSION

[NRC-2010-0278]


NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at 
Nuclear Power Plants, Draft Report for Comment''

AGENCY: Nuclear Regulatory Commission.

ACTION: Announcement of issuance for public comment, availability.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has issued for 
public comment a document entitled: NUREG-1482, Revision 2, 
``Guidelines for Inservice Testing at Nuclear Power Plants, Draft 
Report for Comment,'' and subtitled ``Inservice Testing of Pumps and 
Valves, and Inservice Examination and Testing of Dynamic Restraints 
(Snubbers) at Nuclear Power Plants''.
    (Note that this document was submitted previously for public 
comments as draft NUREG-1946. Based on public comments, draft NUREG-
1482 is being updated as Revision 2 and is being issued to incorporate 
all comments received for draft report NUREG-1946).

DATES: Please submit comments by December 20, 2011. Comments received 
after this date will be considered if it is practical to do so, but the 
NRC staff is able to ensure consideration only for comments received on 
or before this date.

ADDRESSES: Please include Docket ID NRC-2010-0278 in the subject line 
of your comments. For additional instructions on submitting comments 
and instructions on accessing documents related to this action, see 
``Submitting Comments and Accessing Information'' in the SUPPLEMENTARY 
INFORMATION section of this document. 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-
2010-0278. 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.

SUPPLEMENTARY INFORMATION: 

Submitting Comments and Accessing Information

    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 can access publicly available documents related to this 
document 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, 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. 
The NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at 
Nuclear Power Plants, Draft Report for Comment,'' and subtitled 
``Inservice Testing of Pumps and Valves, and Inservice Examination and 
Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants'' is 
available electronically under ADAMS Accession Number ML112231412.
     Federal Rulemaking Web Site: Public comments and 
supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID NRC-2010-0278.

FOR FURTHER INFORMATION CONTACT: Gurjendra S. Bedi, Division of 
Component Integrity, Office of Nuclear Reactor Regulation, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone: 301-415-
1393, e-mail: Gurjendra.Bedi@nrc.gov.
    NUREG-1482, Revision 2, ``Guidelines for Inservice Testing at 
Nuclear Power Plants, Draft Report for Comment'' provides updated 
information on applicable regulations for testing of pumps and valves, 
and inservice examination and testing of snubbers. The information in 
NUREG-1482, ``Guidelines for Inservice Testing at Nuclear Plants,'' 
Revision 0, issued April 1995, and Revision 1, issued January 2005, has 
described these topics in the past.
    This NUREG report replaces Revision 0 and Revision 1 of NUREG-1482, 
and is applicable, unless stated otherwise, to all editions and addenda 
of the American Society of Mechanical Engineers (ASME) Code of 
Operation and Maintenance of Nuclear Power Plants (OM Code), which 
Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b) 
incorporates by reference (76 FR 36232-36279), dated June 21, 2011. 
Note that the draft NUREG-1482, Revision 2, is a substantial re-write 
from issuance of draft NUREG-1946 (ADAMS

[[Page 52356]]

Accession Number: ML102100236). This draft NUREG-1482, Revision 2, 
incorporates all the public comments received for draft NUREG-1946, 
because based on public comments, NUREG-1482, Revision 1, is revised 
and updated instead of issuing the new NUREG-1946. The NRC staff 
evaluation and resolution of public comments for draft NUREG-1946, 
including Inservice Testing Owner Group comments, are documented in 
ADAMS Accession Number: ML112092872. Most of the draft NUREG-1946 
included in the main text of draft NUREG-1482, Revision 2, Appendix A, 
to this NUREG-1482, Revision 2, contains guidance provided in Revision 
1 to NUREG-1482 for pumps and valves that has been updated for the 
development of inservice testing programs at nuclear power plants. 
Appendix B to this NUREG contains guidance related to inservice 
examination and testing of dynamic restraints (snubbers), which is 
included for the first time in the draft NUREG-1482, Revision 2.
    The guidelines and recommendations provided in this NUREG and its 
Appendices A and B do not supersede the regulatory requirements 
specified in 10 CFR 50.55a. Further, this NUREG does not authorize the 
use of alternatives to, or grant relief from, the ASME Code 
requirements for inservice testing of pumps and valves, or inservice 
examination and testing of dynamic restraints (snubbers), incorporated 
by reference in 10 CFR 50.55a. In addition, the NUREG discusses other 
inservice test program topics such as the NRC process for review of the 
OM Code, conditions on the use of the OM Code, and interpretations of 
the OM Code.

    Dated at Rockville, Maryland, this 11th day of August 2011.

    For the Nuclear Regulatory Commission.
Anthony C. McMurtray,
Chief, Component Performance and Testing Branch, Division of Component 
Integrity, Office of Nuclear Reactor Regulation.
[FR Doc. 2011-21357 Filed 8-19-11; 8:45 am]
BILLING CODE 7590-01-P