[Federal Register Volume 75, Number 147 (Monday, August 2, 2010)]
[Notices]
[Page 45173]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-18886]



[[Page 45173]]

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NUCLEAR REGULATORY COMMISSION

[NRC-2008-0638]


Notice of Issuance of Regulatory Guide

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Regulatory Guide 1.151, 
Revision 1, ``Instrument Sensing Lines.''

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FOR FURTHER INFORMATION CONTACT: Karl J. Sturzebecher, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 251-
7494 or e-mail [email protected].

SUPPLEMENTARY INFORMATION:

I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision 
to an existing guide in the agency's ``Regulatory Guide'' series. This 
series was developed to describe and make available to the public 
information such as methods that are acceptable to the NRC staff for 
implementing specific parts of the agency's regulations, techniques 
that the staff uses in evaluating specific problems or postulated 
accidents, and data that the staff needs in its review of applications 
for permits and licenses.
    Revision 1 of Regulatory Guide 1.151 was issued with a temporary 
identification as Draft Regulatory Guide, DG-1178. This guide describes 
a method that the staff of the NRC considers acceptable for use in 
complying with the agency's regulations with respect to the design and 
installation of safety-related instrument sensing lines in nuclear 
power plants. To meet these objectives, the sensing lines must serve a 
safety-related function to prevent the release of reactor coolant as a 
part of the reactor coolant pressure boundary and to provide adequate 
connections to the reactor coolant system for measuring process 
variables (e.g., pressure, level, and flow). The term ``safety-
related'' refers to those structures, systems, and components necessary 
to ensure (1) the integrity of the reactor coolant pressure boundary, 
(2) the capability to shut down the reactor and maintain it in a safe-
shutdown condition, or (3) the capability to prevent or mitigate the 
consequences of accidents that could result in potential offsite 
exposures comparable to the guideline exposures in Title 10, of the 
Code of Federal Regulations, Part 100, ``Reactor Site Criteria'' (10 
CFR Part 100).

II. Further Information

    In December 2008, DG-1178 was published with a public comment 
period of 60 days from the issuance of the guide. The public comment 
period closed on February 6, 2009. The staff's responses to the 
comments received are located in the NRC's Agencywide Documents Access 
and Management System (ADAMS) under Accession No. ML092330222. The 
regulatory analysis may be found in ADAMS under Accession No. 
ML102040145. Electronic copies of Regulatory Guide 1.151, Revision 1 
are available through the NRC's public Web site under ``Regulatory 
Guides'' at http://www.nrc.gov/reading-rm/doc-collections/.
    In addition, regulatory guides are available for inspection at the 
NRC's Public Document Room (PDR) located at Room O-1F21, One White 
Flint North, 11555 Rockville Pike, Rockville, Maryland 20852-2738. The 
PDR's mailing address is USNRC PDR, Washington, DC 20555-0001. The PDR 
can also be reached by telephone at (301) 415-4737 or (800) 397-4209, 
by fax at (301) 415-3548, and by e-mail to [email protected].
    Regulatory guides are not copyrighted, and NRC approval is not 
required to reproduce them.

    Dated at Rockville, Maryland, this 23rd day of July 2010.

    For the Nuclear Regulatory Commission.
Harriet Karagiannis,
Acting Chief, Regulatory Guide Development Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2010-18886 Filed 7-30-10; 8:45 am]
BILLING CODE 7590-01-P