81 FR 88710 - Withdrawal of Regulatory Guides 1.3, 1.4, and 1.5

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 81, Issue 236 (December 8, 2016)

The U.S. Nuclear Regulatory Commission (NRC) is withdrawing three regulatory guides (RGs): RG 1.3, Revision 2, ``Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors,'' dated June 1974; RG 1.4, Revision 2, ``Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors,'' dated June 1974; and RG 1.5 (Safety Guide 5), ``Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors,'' dated March 1971. These three RGs are being withdrawn because the guidance contained in them has been superseded and is now incorporated into RG 1.183, ``Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,'' and RG 1.195, ``Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors.''

[Federal Register Volume 81, Number 236 (Thursday, December 8, 2016)]
[Notices]
[Page 88710]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2016-29407]



[[Page 88710]]

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NUCLEAR REGULATORY COMMISSION

[NRC-2016-0246]


Withdrawal of Regulatory Guides 1.3, 1.4, and 1.5

AGENCY: Nuclear Regulatory Commission.

ACTION: Regulatory Guides 1.3, 1.4, and 1.5; withdrawal.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing 
three regulatory guides (RGs): RG 1.3, Revision 2, ``Assumptions Used 
for Evaluating the Potential Radiological Consequences of a Loss of 
Coolant Accident for Boiling Water Reactors,'' dated June 1974; RG 1.4, 
Revision 2, ``Assumptions Used for Evaluating the Potential 
Radiological Consequences of a Loss of Coolant Accident for Pressurized 
Water Reactors,'' dated June 1974; and RG 1.5 (Safety Guide 5), 
``Assumptions Used for Evaluating the Potential Radiological 
Consequences of a Steam Line Break Accident for Boiling Water 
Reactors,'' dated March 1971. These three RGs are being withdrawn 
because the guidance contained in them has been superseded and is now 
incorporated into RG 1.183, ``Alternative Radiological Source Terms for 
Evaluating Design Basis Accidents at Nuclear Power Reactors,'' and RG 
1.195, ``Methods and Assumptions for Evaluating Radiological 
Consequences of Design Basis Accidents at Light-Water Nuclear Power 
Reactors.''

DATES: The effective date of the withdrawal of RGs 1.3, 1.4, and 1.5 is 
December 8, 2016.

ADDRESSES: Please refer to Docket ID NRC-2016-0246 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2016-0246. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact 
the individuals listed in the FOR FURTHER INFORMATION CONTACT section 
of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to [email protected]. The 
ADAMS accession number for each document referenced in this document 
(if that document is available in ADAMS) is provided the first time 
that a document is referenced. The withdrawal notices for RGs 1.3, 1.4, 
and 1.5 are available in ADAMS under Accession No. ML16210A319.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: John Parillo, Office of Nuclear 
Reactor Regulation, telephone: 301-415-1344; email 
[email protected]; or Mark Orr, Office of Nuclear Regulatory 
Research, telephone: 301-415-6003; email: [email protected]. Both are 
staff of the U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001.

SUPPLEMENTARY INFORMATION: Regulatory guides may be withdrawn by the 
NRC when their guidance no longer provides useful information, or is 
superseded by technological innovations, congressional actions, or 
other events. The withdrawal of an RG should be thought of as the final 
revision of the guide.
    The NRC is withdrawing RG 1.3, Revision 2, ``Assumptions Used for 
Evaluating the Potential Radiological Consequences of a Loss of Coolant 
Accident for Boiling Water Reactors,'' dated June 1974 (ADAMS Accession 
No. ML16215A353); RG 1.4, Revision 2, ``Assumptions Used for Evaluating 
the Potential Radiological Consequences of a Loss of Coolant Accident 
for Pressurized Water Reactors,'' dated June 1974 (ADAMS Accession No. 
ML16215A351); and RG 1.5 (Safety Guide 5), ``Assumptions Used for 
Evaluating the Potential Radiological Consequences of a Steam Line 
Break Accident for Boiling Water Reactors,'' dated March 1971 (ADAMS 
Accession No. ML16215A352).
    The NRC is withdrawing these three RGs because the guidance 
contained in them has been superseded by more current guidance which 
has been incorporated into RG 1.183, ``Alternative Radiological Source 
Terms for Evaluating Design Basis Accidents at Nuclear Power 
Reactors,'' (ADAMS Accession No. ML003716792), and RG 1.195, ``Methods 
and Assumptions for Evaluating Radiological Consequences of Design 
Basis Accidents at Light-Water Nuclear Power Reactors,'' (ADAMS 
Accession No. ML031490640). The information in RG 1.183 provides 
guidance for new and existing light-water reactor (LWR) plants that 
have adopted the alternative source term (AST), and RG 1.195 provides 
guidance for those LWR plants that have not adopted the AST.
    The withdrawal of RGs 1.3, 1.4, and 1.5 does not alter any prior or 
existing NRC licensing approval or the acceptability of licensee 
commitments to these RGs. Although RGs 1.3, 1.4, and 1.5 are withdrawn, 
current licensees may continue to use them, and withdrawal does not 
affect any existing licenses or agreements. However, by withdrawing RGs 
1.3, 1.4, and 1.5, the NRC no longer approves for use the guidance in 
these RGs in future requests or applications for NRC licensing actions.

    Dated at Rockville, Maryland, this 2nd day of December, 2016.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Chief, Regulatory Guidance and Generic Issues Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2016-29407 Filed 12-7-16; 8:45 am]
 BILLING CODE 7590-01-P