Withdrawal of Regulatory Guide, 58324 [E9-27058]

Download as PDF 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 RG 1.83 is being withdrawn because it no longer describes a preferred approach.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

[Federal Register Volume 74, Number 217 (Thursday, November 12, 2009)]
[Notices]
[Page 58324]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-27058]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2009-0488]


Withdrawal of Regulatory Guide

AGENCY: Nuclear Regulatory Commission.

ACTION: Withdrawal of Regulatory Guide 1.83.

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

FOR FURTHER INFORMATION CONTACT: John N. Ridgely, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone: 301-251-
7458 or e-mail 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 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 risk-informed 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 
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/doc-collections. 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
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