81_FR_88946 81 FR 88710 - Withdrawal of Regulatory Guides 1.3, 1.4, and 1.5

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)

Page Range88710-88710
FR Document2016-29407

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 These three RGs are being withdrawn because the guidance contained in them has been superseded and is now incorporated into RG 1.183, ``Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,'' and RG 1.195,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 Issue 236 (Thursday, December 8, 2016) 
[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

88710 Federal Register / Vol. 81, No. 236 / Thursday, December 8, 2016 / Notices NUCLEAR REGULATORY select ‘‘Begin Web-based ADAMS Nuclear Power Reactors,’’ (ADAMS COMMISSION Search.’’ For problems with ADAMS, Accession No. ML031490640). The please contact the NRC’s Public information in RG 1.183 provides [NRC–2016–0246] Document Room (PDR) reference staff at guidance for new and existing light- Withdrawal of Regulatory Guides 1.3, 1–800–397–4209, 301–415–4737, or by water reactor (LWR) plants that have 1.4, and 1.5 email to pdr.resource@nrc.gov. The adopted the alternative source term ADAMS accession number for each (AST), and RG 1.195 provides guidance AGENCY: Nuclear Regulatory document referenced in this document for those LWR plants that have not Commission. (if that document is available in adopted the AST. ACTION: Regulatory Guides 1.3, 1.4, and ADAMS) is provided the first time that The withdrawal of RGs 1.3, 1.4, and 1.5; withdrawal. a document is referenced. The 1.5 does not alter any prior or existing withdrawal notices for RGs 1.3, 1.4, and NRC licensing approval or the SUMMARY: The U.S. Nuclear Regulatory 1.5 are available in ADAMS under acceptability of licensee commitments Commission (NRC) is withdrawing three Accession No. ML16210A319. to these RGs. Although RGs 1.3, 1.4, and regulatory guides (RGs): RG 1.3, • NRC’s PDR: You may examine and 1.5 are withdrawn, current licensees Revision 2, ‘‘Assumptions Used for purchase copies of public documents at may continue to use them, and Evaluating the Potential Radiological the NRC’s PDR, Room O1–F21, One withdrawal does not affect any existing Consequences of a Loss of Coolant White Flint North, 11555 Rockville licenses or agreements. However, by Accident for Boiling Water Reactors,’’ Pike, Rockville, Maryland 20852. withdrawing RGs 1.3, 1.4, and 1.5, the dated June 1974; RG 1.4, Revision 2, FOR FURTHER INFORMATION CONTACT: John NRC no longer approves for use the ‘‘Assumptions Used for Evaluating the Parillo, Office of Nuclear Reactor guidance in these RGs in future requests Potential Radiological Consequences of Regulation, telephone: 301–415–1344; or applications for NRC licensing a Loss of Coolant Accident for email John.Parillo@nrc.gov; or Mark Orr, actions. Pressurized Water Reactors,’’ dated June Office of Nuclear Regulatory Research, Dated at Rockville, Maryland, this 2nd day 1974; and RG 1.5 (Safety Guide 5), telephone: 301–415–6003; email: of December, 2016. ‘‘Assumptions Used for Evaluating the Mark.Orr@nrc.gov. Both are staff of the For the Nuclear Regulatory Commission. Potential Radiological Consequences of U.S. Nuclear Regulatory Commission, Thomas H. Boyce, a Steam Line Break Accident for Boiling Washington, DC 20555–0001. Water Reactors,’’ dated March 1971. Chief, Regulatory Guidance and Generic SUPPLEMENTARY INFORMATION: Regulatory Issues Branch, Division of Engineering, Office These three RGs are being withdrawn guides may be withdrawn by the NRC of Nuclear Regulatory Research. because the guidance contained in them when their guidance no longer provides [FR Doc. 2016–29407 Filed 12–7–16; 8:45 am] has been superseded and is now useful information, or is superseded by BILLING CODE 7590–01–P incorporated into RG 1.183, technological innovations, ‘‘Alternative Radiological Source Terms congressional actions, or other events. for Evaluating Design Basis Accidents at The withdrawal of an RG should be NUCLEAR REGULATORY Nuclear Power Reactors,’’ and RG 1.195, thought of as the final revision of the COMMISSION ‘‘Methods and Assumptions for guide. Evaluating Radiological Consequences The NRC is withdrawing RG 1.3, [NRC–2015–0203] of Design Basis Accidents at Light-Water Revision 2, ‘‘Assumptions Used for Nuclear Power Reactors.’’ Instructions for Recording and Evaluating the Potential Radiological Reporting Occupational Radiation DATES: The effective date of the Consequences of a Loss of Coolant withdrawal of RGs 1.3, 1.4, and 1.5 is Dose Data Accident for Boiling Water Reactors,’’ December 8, 2016. dated June 1974 (ADAMS Accession No. AGENCY: Nuclear Regulatory ADDRESSES: Please refer to Docket ID ML16215A353); RG 1.4, Revision 2, Commission. NRC–2016–0246 when contacting the ‘‘Assumptions Used for Evaluating the ACTION: Regulatory guide; issuance. NRC about the availability of Potential Radiological Consequences of information regarding this document. a Loss of Coolant Accident for SUMMARY: The U.S. Nuclear Regulatory You may obtain publicly-available Pressurized Water Reactors,’’ dated June Commission (NRC) is issuing Revision 3 information related to this document 1974 (ADAMS Accession No. to Regulatory Guide (RG) 8.7, using any of the following methods: ML16215A351); and RG 1.5 (Safety ‘‘Instructions for Recording and • Federal Rulemaking Web site: Go to Guide 5), ‘‘Assumptions Used for Reporting Occupational Radiation Dose http://www.regulations.gov and search Evaluating the Potential Radiological Data.’’ Regulatory Guide 8.7 describes for Docket ID NRC–2016–0246. Address Consequences of a Steam Line Break methods that the staff of NRC considers questions about NRC dockets to Carol Accident for Boiling Water Reactors,’’ acceptable for licensees to use for the Gallagher; telephone: 301–415–3463; dated March 1971 (ADAMS Accession preparation, retention, and reporting of email: Carol.Gallagher@nrc.gov. For No. ML16215A352). records of occupational radiation doses. technical questions, contact the The NRC is withdrawing these three Revision 3 addresses changes to individuals listed in the FOR FURTHER RGs because the guidance contained in applicable NRC regulations and related INFORMATION CONTACT section of this them has been superseded by more staff practices since Revision 2 was document. current guidance which has been issued in November 2005. Revision 3 • NRC’s Agencywide Documents incorporated into RG 1.183, includes changes in the process a sradovich on DSK3GMQ082PROD with NOTICES Access and Management System ‘‘Alternative Radiological Source Terms licensee needs to follow in order to (ADAMS): You may obtain publicly- for Evaluating Design Basis Accidents at monitor occupational exposure, available documents online in the Nuclear Power Reactors,’’ (ADAMS determine prior doses, record ADAMS Public Documents collection at Accession No. ML003716792), and RG monitoring results, and report the http://www.nrc.gov/reading-rm/ 1.195, ‘‘Methods and Assumptions for results, when required. In addition, adams.html. To begin the search, select Evaluating Radiological Consequences Revision 3 references revised versions of ‘‘ADAMS Public Documents’’ and then of Design Basis Accidents at Light-Water NRC Form 4, ‘‘Cumulative Occupational VerDate Sep<11>2014 17:28 Dec 07, 2016 Jkt 241001 PO 00000 Frm 00054 Fmt 4703 Sfmt 4703 E:\FR\FM\08DEN1.SGM 08DEN1


Document Created: 2016-12-08 00:26:55
Document Modified: 2016-12-08 00:26:55
CategoryRegulatory Information
CollectionFederal Register
sudoc ClassAE 2.7:
GS 4.107:
AE 2.106:
PublisherOffice of the Federal Register, National Archives and Records Administration
SectionNotices
ActionRegulatory Guides 1.3, 1.4, and 1.5; withdrawal.
DatesThe effective date of the withdrawal of RGs 1.3, 1.4, and 1.5 is December 8, 2016.
ContactJohn 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.
FR Citation81 FR 88710 
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