Office of New Reactors; Proposed Interim Staff Guidance; Review of Evaluation To Address Gas Accumulation Issues in Safety Related Systems, 58323-58324 [E9-27151]

Download as PDF Federal Register / Vol. 74, No. 217 / Thursday, November 12, 2009 / Notices NUCLEAR REGULATORY COMMISSION [NRC–2009–0110] Office of New Reactors; Final Interim Staff Guidance on Review of Evaluation To Address Adverse Flow Effects in Equipment Other Than Reactor Internals jlentini on DSKJ8SOYB1PROD with NOTICES AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Notice of availability. SUMMARY: The NRC is issuing its Final Interim Staff Guidance (ISG) DC/COL– ISG–010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092890285). The purpose of this ISG is to modify and provide additional clarity in the guidance for the review of analyses of adverse flow effects in equipment other than reactor internals performed by combined license (COL) and design certification (DC) applicants. This ISG would revise the staff guidance previously issued in March 2007 in the Standard Review Plan (SRP) NUREG 0080, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,’’ Section 3.9.2, ‘‘Dynamic Testing and Analysis of Systems, Structures, and Components,’’ Section 3.9.5, ‘‘Reactor Pressure Vessel Internals,’’ and Regulatory Guide 1.20, ‘‘Comprehensive Vibration Assessment Program for Reactor Internals During Pre-Operational and Initial Startup Testing.’’ The NRC staff issues DC/COL– ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DCs and COLs by the Office of New Reactors. The NRC staff will also incorporate the approved DC/ COL–ISG–010 into the next revision of the SRP and related guidance documents. Disposition: On March 9, 2009, the NRC staff issued the proposed DC/COL– ISG–010 on ‘‘Disposition of Review of Evaluation to Address Adverse Flow Effects in Equipment Other than Reactor Internals,’’ ADAMS Accession No. ML090510728. There were no comments received on the proposed ISG. Therefore, the guidance is issued as final with only minor editorial changes to the proposed notification as above. ADDRESSES: The NRC ADAMS provides text and image files of NRC’s public documents. These documents may be accessed through the NRC’s Public Electronic Reading Room on the Internet at https://www.nrc.gov/reading-rm/ adams.html. Persons who do not have access to ADAMS or who encounter VerDate Nov<24>2008 16:12 Nov 10, 2009 Jkt 220001 problems in accessing the documents located in ADAMS should contact the NRC Public Document Room reference staff by telephone at 1–800–397–4209, 301–415–4737, or by e-mail at pdr.resource@nrc.gov. FOR FURTHER INFORMATION CONTACT: Ms. Jennifer L. Dixon-Herrity, Chief, Engineering Mechanics Branch 2, Division of Engineering, Office of the New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone at 301–415–2967 or by e-mail at jennifer.dixon-herrity@nrc.gov. SUPPLEMENTARY INFORMATION: The agency posts its issued staff guidance in the agency external Web page (https:// www.nrc.gov/reading-rm/doccollections/isg/). Dated at Rockville, Maryland, this 3rd day of November 2009. For the Nuclear Regulatory Commission. William F. Burton, Branch Chief, Rulemaking and Guidance Development Branch, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. E9–27154 Filed 11–10–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0494] Office of New Reactors; Proposed Interim Staff Guidance; Review of Evaluation To Address Gas Accumulation Issues in Safety Related Systems AGENCY: Nuclear Regulatory Commission (NRC). ACTION: Solicitation of public comment. SUMMARY: The NRC staff is soliciting public comment on its proposed Interim Staff Guidance (ISG) DC/COL–ISG–019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092360375). The purpose of this ISG is to clarify the NRC staff guidance to address issues of gas accumulation in safety related systems. This ISG revises and updates the guidance provided to the staff in Standard Review Plan (SRP) Sections 5.4.7, ‘‘Residual Heat Removal System,’’ 6.3 ‘‘Emergency Core Cooling System,’’ and 6.5.2 ‘‘Containment Spray System’’ of NUREG–0800, ‘‘Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,’’ March 2007. The NRC staff issues DC/ COL–ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for design certifications and combined PO 00000 Frm 00085 Fmt 4703 Sfmt 4703 58323 licenses by the Office of New Reactors. The NRC staff intends to incorporate the final approved DC/COL–ISG–019 into the next revision of the SRP and related guidance documents. DATES: Comments must be filed no later than 30 days from the date of publication of this notice in the Federal Register. Comments received after this date will be considered, if it is practical to do so, but the Commission is able to ensure consideration only for comments received on or before this date. ADDRESSES: You may submit comments by any one of the following methods. Please include Docket ID NRC–2009– 0494 in the subject line of your comments. Comments submitted in writing or in electronic form will be posted on the NRC Web site and on the Federal rulemaking Web site 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. Federal Rulemaking Web site: Go to https://www.regulations.gov and search for documents filed under Docket ID NRC–2009–0494. Address questions about NRC dockets to Carol Gallagher 301–492–3668; e-mail Carol.Gallagher@nrc.gov. Mail comments to: Michael T. Lesar, Chief, Rulemaking and Directives Branch (RDB), Division of Administrative Services, Office of Administration, Mail Stop: TWB–05– B01M, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, or by fax to RDB at (301) 492– 3446. The NRC ADAMS provides text and image files of NRC’s public documents. These documents may be accessed through the NRC’s Public Electronic Reading Room on the Internet at https://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 Public Document Room reference staff at 1–800–397–4209, 301–415–4737, or by e-mail at PDR.Resource@nrc.gov. E:\FR\FM\12NON1.SGM 12NON1 58324 Federal Register / Vol. 74, No. 217 / Thursday, November 12, 2009 / Notices FOR FURTHER INFORMATION CONTACT: Mr. Joseph E. Donoghue, Chief, Reactor Systems, Nuclear Performance and Code Review Branch, Division of Safety Systems & Risk Assessment, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone 301–415–1193 or e-mail at joseph.donoghue@nrc.gov. SUPPLEMENTARY INFORMATION: The agency posts its issued staff guidance in the agency external Web page (https:// www.nrc.gov/reading-rm/doccollections/isg/). The NRC staff is issuing this notice to solicit public comments on the proposed DC/COL–ISG–019. After the NRC staff considers any public comments, it will make a determination regarding the proposed DC/COL–ISG– 019. Dated at Rockville, Maryland, this 3rd day of November 2009. For the Nuclear Regulatory Commission. William F. Burton, Branch Chief, Rulemaking and Guidance Development Branch, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. E9–27151 Filed 11–10–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0488] Withdrawal of Regulatory Guide AGENCY: Nuclear Regulatory Commission. ACTION: Withdrawal of Regulatory Guide 1.83. jlentini on DSKJ8SOYB1PROD with NOTICES FOR FURTHER INFORMATION CONTACT: John N. Ridgely, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, telephone: 301–251–7458 or email John.Ridgely@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC or Commission) is withdrawing Regulatory Guide (RG) 1.83, ‘‘Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes,’’ Revision 1, which was issued July 1975. RG 1.83 describes a program of periodic inservice inspection and nondestructive examination using a prescriptive sampling approach of steam generator tubing to detect defects and deterioration of the tubes in pressurized water reactors (PWRs). The RG was developed to demonstrate compliance with portions of General Design Criterion (GDC) 14, ‘‘Reactor Coolant VerDate Nov<24>2008 16:12 Nov 10, 2009 Jkt 220001 Pressure Boundary,’’ GDC 15, ‘‘Reactor Coolant System Design,’’ GDC 31, ‘‘Fracture Prevention of Reactor Coolant Pressure Boundary,’’ and GDC 32, ‘‘Inspection of Reactor Coolant Pressure Boundary.’’ RG 1.83 is being withdrawn because it no longer describes a preferred approach. It is a prescriptive regulatory guide which recommends the use of eddy current testing for the inspection of steam generator tubes. RG 1.83 may not ensure steam generator tube integrity as required by other rules/ regulations. In addition, many of the methods/techniques discussed in the regulatory guide would not be considered acceptable, feasible, or practical given improvements in technology. Given the technological improvements and the recognition of the importance of maintaining tube integrity from a safety and economic perspective, the need for such prescriptive guidance has been superseded. In addition, simply following this guidance may not be sufficient to ensure tube integrity consistent with NRC regulations. The NRC now endorses a more riskinformed and performance-based approach to regulatory compliance. The performance-based approach relies upon measurable (or calculable) outcomes (i.e., performance results) to be met, but provides more flexibility to the licensee as to the means of meeting those outcomes. The high level requirements that must be met are contained in the standard technical specifications. These technical specifications are based on Nuclear Energy Institute (NEI) 97–06, ‘‘Steam Generator Program Guidelines,’’ and Technical Specification Task Force (TSTF) Traveller, TSTF–449. This latter document has been reviewed and approved by the NRC staff as documented in Generic Letter 2006–01. In addition, the current version of this Standard Review Plan discusses the high level requirements which an acceptable steam generator program must meet. RG 1.83 is no longer needed since the NRC has adopted the performance-based approach. The use of a performance-based approach to steam generator tube inspection does not supplant or displace the requirement for compliance with NRC regulations. II. Further Information Withdrawal of RG 1.83 does not, in and of itself, alter any prior or existing licensing commitments based on its use. The guidance provided in this regulatory guide is no longer necessary. Regulatory guides may be withdrawn when their guidance is superseded by PO 00000 Frm 00086 Fmt 4703 Sfmt 4703 Congressional action, the methods or techniques described in the Regulatory Guide no longer describe a preferred approach, or the Regulatory Guide does not provide useful information. Regulatory guides are available for inspection or downloading through the NRC’s public Web site under ‘‘Regulatory Guides’’ in the NRC’s Electronic Reading Room at https:// www.nrc.gov/reading-rm/doccollections. Regulatory guides are also available for inspection at the NRC’s Public Document Room (PDR), Room O– 1 F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852– 2738. The PDR’s mailing address is US NRC PDR, Washington, DC 20555–0001. You can reach the staff by telephone at 301–415–4737 or 800–397–4209, by fax at 301–415–3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. Dated at Rockville, Maryland, this 3rd day of November 2009. For the Nuclear Regulatory Commission. John N. Ridgely, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E9–27058 Filed 11–10–09; 8:45 am] BILLING CODE 7590–01–P OFFICE OF PERSONNEL MANAGEMENT Proposed Collection; Comment Request for Review of a Revised Information Collection: (OMB Control No. 3206–0208; Form RI 38–115) AGENCY: Office of Personnel Management. ACTION: Notice. SUMMARY: In accordance with the Paperwork Reduction Act of 1995 (Pub. L. 104–13, May 22, 1995), this notice announces that the Office of Personnel Management (OPM) intends to submit to the Office of Management and Budget (OMB) a request for review of a revised information collection. This information collection, ‘‘Representative Payee Survey’’ (OMB Control No. 3206–0208, Form RI 38–115), is used to collect information about how the benefits paid to a representative payee have been used or conserved for the benefit of the incompetent annuitant. Comments are particularly invited on: whether this collection of information is necessary for the proper performance of functions of the Office of Personnel Management, and whether it will have practical utility; whether our estimate of E:\FR\FM\12NON1.SGM 12NON1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 74, Number 217 (Thursday, November 12, 2009)]
[Notices]
[Pages 58323-58324]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-27151]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2009-0494]


Office of New Reactors; Proposed Interim Staff Guidance; Review 
of Evaluation To Address Gas Accumulation Issues in Safety Related 
Systems

AGENCY: Nuclear Regulatory Commission (NRC).

ACTION: Solicitation of public comment.

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

SUMMARY: The NRC staff is soliciting public comment on its proposed 
Interim Staff Guidance (ISG) DC/COL-ISG-019 (Agencywide Documents 
Access and Management System (ADAMS) Accession No. ML092360375). The 
purpose of this ISG is to clarify the NRC staff guidance to address 
issues of gas accumulation in safety related systems. This ISG revises 
and updates the guidance provided to the staff in Standard Review Plan 
(SRP) Sections 5.4.7, ``Residual Heat Removal System,'' 6.3 ``Emergency 
Core Cooling System,'' and 6.5.2 ``Containment Spray System'' of NUREG-
0800, ``Standard Review Plan for the Review of Safety Analysis Reports 
for Nuclear Power Plants,'' March 2007. The NRC staff issues DC/COL-
ISGs to facilitate timely implementation of current staff guidance and 
to facilitate activities associated with review of applications for 
design certifications and combined licenses by the Office of New 
Reactors. The NRC staff intends to incorporate the final approved DC/
COL-ISG-019 into the next revision of the SRP and related guidance 
documents.

DATES: Comments must be filed no later than 30 days from the date of 
publication of this notice in the Federal Register. Comments received 
after this date will be considered, if it is practical to do so, but 
the Commission is able to ensure consideration only for comments 
received on or before this date.

ADDRESSES: You may submit comments by any one of the following methods. 
Please include Docket ID NRC-2009-0494 in the subject line of your 
comments. Comments submitted in writing or in electronic form will be 
posted on the NRC Web site and on the Federal rulemaking Web site 
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.
    Federal Rulemaking Web site: Go to https://www.regulations.gov and 
search for documents filed under Docket ID NRC-2009-0494. Address 
questions about NRC dockets to Carol Gallagher 301-492-3668; e-mail 
Carol.Gallagher@nrc.gov.
    Mail comments to: Michael T. Lesar, Chief, Rulemaking and 
Directives Branch (RDB), Division of Administrative Services, Office of 
Administration, Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, or by fax to RDB at (301) 492-
3446.
    The NRC ADAMS provides text and image files of NRC's public 
documents. These documents may be accessed through the NRC's Public 
Electronic Reading Room on the Internet at https://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 Public Document Room reference staff at 1-800-397-4209, 301-415-
4737, or by e-mail at PDR.Resource@nrc.gov.

[[Page 58324]]


FOR FURTHER INFORMATION CONTACT: Mr. Joseph E. Donoghue, Chief, Reactor 
Systems, Nuclear Performance and Code Review Branch, Division of Safety 
Systems & Risk Assessment, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone 301-415-1193 or e-mail at 
joseph.donoghue@nrc.gov.

SUPPLEMENTARY INFORMATION: The agency posts its issued staff guidance 
in the agency external Web page (https://www.nrc.gov/reading-rm/doc-collections/isg/).
    The NRC staff is issuing this notice to solicit public comments on 
the proposed DC/COL-ISG-019. After the NRC staff considers any public 
comments, it will make a determination regarding the proposed DC/COL-
ISG-019.

    Dated at Rockville, Maryland, this 3rd day of November 2009.

    For the Nuclear Regulatory Commission.
William F. Burton,
Branch Chief, Rulemaking and Guidance Development Branch, Division of 
New Reactor Licensing, Office of New Reactors.
[FR Doc. E9-27151 Filed 11-10-09; 8:45 am]
BILLING CODE 7590-01-P

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