Alternative Method for Calculating Embrittlement for Steel Reactor Vessels, 63819-63820 [2019-24936]

Download as PDF Federal Register / Vol. 84, No. 223 / Tuesday, November 19, 2019 / Proposed Rules Date Document July 12, 2011 ........... October 31, 2012 .... October 29, 2015 .... March 12, 2012 ....... March 12, 2012 ....... February 8, 2016 ..... January 24, 2019 .... Dated at Rockville, Maryland, this 14th day of November, 2019. For the Nuclear Regulatory Commission. Annette L. Vietti-Cook, Secretary of the Commission. [FR Doc. 2019–25018 Filed 11–18–19; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 [Docket No. PRM–50–120; NRC–2019–0180] Alternative Method for Calculating Embrittlement for Steel Reactor Vessels Nuclear Regulatory Commission. ACTION: Petition for rulemaking; notice of docketing, and request for comment. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Thomas A. Bergman, on behalf of NuScale Power, LLC, dated August 19, 2019, requesting that the NRC revise its regulations to alleviate a requirement for calculating the embrittlement for advanced reactor designs and to add the embrittlement trend curve formula for calculating the mean value of the transition temperature shift described in American Society for Testing and Materials E900– khammond on DSKJM1Z7X2PROD with PROPOSALS SUMMARY: VerDate Sep<11>2014 ADAMS Accession No./website/Federal Register citation SECY–11–0093—Enclosure: The Near Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident. NUREG–1635, Volume 10, ‘‘Review and Evaluation of the Nuclear Regulatory Commission Safety Research Program: A Report to the U.S. Nuclear Regulatory Commission’’. SECY–15–0137, ‘‘Proposed Plan for Resolving Open Fukushima Tier 2 and 3 Recommendations’’. EA–12–049 ‘‘Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events’’. EA–12–051, ‘‘Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation’’. SRM–SECY–15–0137—Proposed Plans for Resolving Open Fukushima Tier 2 and 3 Recommendations. SRM–M190124A: Affirmation Session-SECY–16–0142: Final Rule: Mitigation of Beyond-Design-Basis Events (RIN 3150–AJ49). IV. Conclusion For the reasons cited in Section II of this document, the NRC is denying PRM–50–111. The NRC finds that the existing regulations provide a sufficient level of safety such that additional requirements are not necessary. Therefore, installation of in-core temperature monitoring devices need not be required by regulation. 16:09 Nov 18, 2019 Jkt 250001 ML111861807. ML12311A417. ML15254A006. ML12054A735. ML12056A044. ML16039A175. ML19024A073. 152 to the NRC’s regulations and guidance documents. The petition was docketed by the NRC on September 11, 2019, and has been assigned Docket No. PRM–50–120. The NRC is examining the issues raised in PRM–50–120 to determine whether these issues should be considered in rulemaking. The NRC is requesting public comment on this petition at this time. DATES: Submit comments by December 19, 2019. Comments received after this date will be considered if it is practical to do so, but the NRC is able to assure consideration only for comments received on or before this date. ADDRESSES: You may submit comments by any of the following methods: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2019–0180. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • Email comments to: Rulemaking.Comments@nrc.gov. If you do not receive an automatic email reply confirming receipt, then contact us at 301–415–1677. • Fax comments to: Secretary, U.S. Nuclear Regulatory Commission at 301– 415–1101. • Mail comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, ATTN: Rulemakings and Adjudications Staff. • Hand deliver comments to: 11555 Rockville Pike, Rockville, Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal workdays; telephone: 301–415–1677. For additional direction on obtaining information and submitting comments, PO 00000 Frm 00004 63819 Fmt 4702 Sfmt 4702 see ‘‘Obtaining Information and Submitting Comments’’ in the SUPPLEMENTARY INFORMATION section of this document. FOR FURTHER INFORMATION CONTACT: Yanely Malave-Velez, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–415–1519; email Yanely.MalaveVelez@nrc.gov. SUPPLEMENTARY INFORMATION: I. Obtaining Information and Submitting Comments A. Obtaining Information Please refer to Docket ID NRC–2019– 0180 when contacting the NRC about the availability of information for this action. You may obtain publiclyavailable information related to this action by any of the following methods: • Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC–2019–0180. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, 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 pdr.resource@ nrc.gov. The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One E:\FR\FM\19NOP1.SGM 19NOP1 63820 Federal Register / Vol. 84, No. 223 / Tuesday, November 19, 2019 / Proposed Rules White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. B. Submitting Comments Please include Docket ID NRC–2019– 0180 in your comment submission. The NRC cautions you not to include identifying or contact information that you do not want to be publicly disclosed in your comment submission. The NRC will post all comment submissions at https:// www.regulations.gov as well as enter the comment submissions into ADAMS. The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment into ADAMS. khammond on DSKJM1Z7X2PROD with PROPOSALS II. The Petitioner and the Petition The petition was submitted by Thomas A. Bergman on behalf of NuScale Power, LLC. Thomas A. Bergman is the Vice President of Regulatory Affairs. The petitioner requests that the NRC amend part 50 of title 10 of the Code of Federal Regulations (10 CFR) to alleviate an unnecessarily burdensome requirement on advanced reactor designs by adding an alternative formula for calculating the mean value of the transition temperature shift. The petition can be found in ADAMS at Accession No. ML19254B848. III. Discussion of the Petition The provisions in 10 CFR 50.61 and Regulatory Guide 1.99 were first published in 1988 and focus on determining embrittlement inside the surface of the reactor pressure vessel. Additional irradiation embrittlement data has been collected since the time 10 CFR 50.61 and Regulatory Guide 1.99 were developed. The petitioner states that small modular reactor design is unnecessarily burdened with an excessively conservative methodology for determining radiation embrittlement based on outdated information. The petitioner requests that the NRC amend 10 CFR part 50 to alleviate a requirement for calculating the embrittlement for advanced reactor designs and add the embrittlement trend curve formula for calculating the mean VerDate Sep<11>2014 16:09 Nov 18, 2019 Jkt 250001 value of the transition temperature shift described in American Society for Testing and Materials (ASTM) E900–15 to the NRC’s regulations and guidance documents. The petitioner states that ASTM E900–15 represents the latest industry consensus embrittlement trend correlation and is derived from a much larger database than was available when Regulatory Guide 1.99 was issued and last revised. IV. Conclusion The NRC has determined that the petition meets the threshold sufficiency requirements for docketing a petition for rulemaking under 10 CFR 2.803. The NRC is examining the issues raised in PRM–50–120 to determine whether these issues should be considered in rulemaking and is requesting public comment on this petition at this time. Dated at Rockville, Maryland, this 13th day of November 2019. For the Nuclear Regulatory Commission. Annette L. Vietti-Cook, Secretary of the Commission. [FR Doc. 2019–24936 Filed 11–18–19; 8:45 am] BILLING CODE 7590–01–P FEDERAL RESERVE SYSTEM 12 CFR Part 246 [Regulation TT; Docket No. R–1683] RIN 7100–AF63 Supervision and Regulation Assessments of Fees for Bank Holding Companies and Savings and Loan Holding Companies With Total Consolidated Assets of $100 Billion or More Board of Governors of the Federal Reserve System (Board). ACTION: Notice of proposed rule; correction. AGENCY: The Federal Register document of November 12, 2019 proposing changes to the Board’s Regulation TT provided an expired comment period end date. This document corrects that error. DATES: Comments must be received on or before January 9, 2020. SUPPLEMENTARY INFORMATION: This document corrects the comment period end date in 84 FR 60944 published on November 12, 2019 to read: SUMMARY: Correction DATES: Comments must be received on or before January 9, 2020. PO 00000 Frm 00005 Fmt 4702 Sfmt 4702 Board of Governors of the Federal Reserve System, November 12, 2019. Ann Misback, Secretary of the Board. [FR Doc. 2019–24959 Filed 11–18–19; 8:45 am] BILLING CODE P DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 39 [Docket No. FAA–2019–0683; Product Identifier 2015–NE–02–AD] RIN 2120–AA64 Airworthiness Directives; General Electric Company Turbofan Engines Federal Aviation Administration (FAA), DOT. ACTION: Notice of proposed rulemaking (NPRM). AGENCY: The FAA proposes to supersede Airworthiness Directive (AD) 2017–09–06, which applies to all General Electric Company (GE) GEnx– 1B and GEnx–2B model turbofan engines. AD 2017–09–06 requires updating electronic engine control (EEC) full authority digital electronic control (FADEC) software and replacing a certain fan hub frame assembly part installed on GEnx–2B turbofan engines. Since the FAA issued AD 2017–09–06, GE has developed a design change to remove the unsafe condition. This proposed AD would require removal from service of certain EEC FADEC software on GEnx–1B and GEnx–2B model turbofan engines and would also require replacing the affected fan hub frame assembly booster outlet guide vanes. The FAA is proposing this AD to address the unsafe condition on these products. SUMMARY: The FAA must receive comments on this proposed AD by January 3, 2020. ADDRESSES: You may send comments, using the procedures found in 14 CFR 11.43 and 11.45, by any of the following methods: • Federal eRulemaking Portal: Go to https://www.regulations.gov. Follow the instructions for submitting comments. • Fax: 202–493–2251. • Mail: U.S. Department of Transportation, Docket Operations, M– 30, West Building Ground Floor, Room W12–140, 1200 New Jersey Avenue SE, Washington, DC 20590. • Hand Delivery: Deliver to Mail address above between 9 a.m. and 5 p.m., Monday through Friday, except Federal holidays. DATES: E:\FR\FM\19NOP1.SGM 19NOP1

Agencies

[Federal Register Volume 84, Number 223 (Tuesday, November 19, 2019)]
[Proposed Rules]
[Pages 63819-63820]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2019-24936]


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NUCLEAR REGULATORY COMMISSION

10 CFR Part 50

[Docket No. PRM-50-120; NRC-2019-0180]


Alternative Method for Calculating Embrittlement for Steel 
Reactor Vessels

AGENCY: Nuclear Regulatory Commission.

ACTION: Petition for rulemaking; notice of docketing, and request for 
comment.

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

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) has received a 
petition for rulemaking from Thomas A. Bergman, on behalf of NuScale 
Power, LLC, dated August 19, 2019, requesting that the NRC revise its 
regulations to alleviate a requirement for calculating the 
embrittlement for advanced reactor designs and to add the embrittlement 
trend curve formula for calculating the mean value of the transition 
temperature shift described in American Society for Testing and 
Materials E900-152 to the NRC's regulations and guidance documents. The 
petition was docketed by the NRC on September 11, 2019, and has been 
assigned Docket No. PRM-50-120. The NRC is examining the issues raised 
in PRM-50-120 to determine whether these issues should be considered in 
rulemaking. The NRC is requesting public comment on this petition at 
this time.

DATES: Submit comments by December 19, 2019. Comments received after 
this date will be considered if it is practical to do so, but the NRC 
is able to assure consideration only for comments received on or before 
this date.

ADDRESSES: You may submit comments by any of the following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0180. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     Email comments to: [email protected]. If you do 
not receive an automatic email reply confirming receipt, then contact 
us at 301-415-1677.
     Fax comments to: Secretary, U.S. Nuclear Regulatory 
Commission at 301-415-1101.
     Mail comments to: Secretary, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, ATTN: Rulemakings and 
Adjudications Staff.
     Hand deliver comments to: 11555 Rockville Pike, Rockville, 
Maryland 20852, between 7:30 a.m. and 4:15 p.m. (Eastern Time) Federal 
workdays; telephone: 301-415-1677.
    For additional direction on obtaining information and submitting 
comments, see ``Obtaining Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Yanely Malave-Velez, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone: 301-415-1519; email 
[email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2019-0180 when contacting the NRC 
about the availability of information for this action. You may obtain 
publicly-available information related to this action by any of the 
following methods:
     Federal Rulemaking Website: Go to https://www.regulations.gov and search for Docket ID NRC-2019-0180.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, 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 (if it is available in ADAMS) is provided the first 
time that it is mentioned in this document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One

[[Page 63820]]

White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.

B. Submitting Comments

    Please include Docket ID NRC-2019-0180 in your comment submission.
    The NRC cautions you not to include identifying or contact 
information that you do not want to be publicly disclosed in your 
comment submission. The NRC will post all comment submissions at 
https://www.regulations.gov as well as enter the comment submissions 
into ADAMS. The NRC does not routinely edit comment submissions to 
remove identifying or contact information.
    If you are requesting or aggregating comments from other persons 
for submission to the NRC, then you should inform those persons not to 
include identifying or contact information that they do not want to be 
publicly disclosed in their comment submission. Your request should 
state that the NRC does not routinely edit comment submissions to 
remove such information before making the comment submissions available 
to the public or entering the comment into ADAMS.

II. The Petitioner and the Petition

    The petition was submitted by Thomas A. Bergman on behalf of 
NuScale Power, LLC. Thomas A. Bergman is the Vice President of 
Regulatory Affairs. The petitioner requests that the NRC amend part 50 
of title 10 of the Code of Federal Regulations (10 CFR) to alleviate an 
unnecessarily burdensome requirement on advanced reactor designs by 
adding an alternative formula for calculating the mean value of the 
transition temperature shift. The petition can be found in ADAMS at 
Accession No. ML19254B848.

III. Discussion of the Petition

    The provisions in 10 CFR 50.61 and Regulatory Guide 1.99 were first 
published in 1988 and focus on determining embrittlement inside the 
surface of the reactor pressure vessel. Additional irradiation 
embrittlement data has been collected since the time 10 CFR 50.61 and 
Regulatory Guide 1.99 were developed. The petitioner states that small 
modular reactor design is unnecessarily burdened with an excessively 
conservative methodology for determining radiation embrittlement based 
on outdated information. The petitioner requests that the NRC amend 10 
CFR part 50 to alleviate a requirement for calculating the 
embrittlement for advanced reactor designs and add the embrittlement 
trend curve formula for calculating the mean value of the transition 
temperature shift described in American Society for Testing and 
Materials (ASTM) E900-15 to the NRC's regulations and guidance 
documents. The petitioner states that ASTM E900-15 represents the 
latest industry consensus embrittlement trend correlation and is 
derived from a much larger database than was available when Regulatory 
Guide 1.99 was issued and last revised.

IV. Conclusion

    The NRC has determined that the petition meets the threshold 
sufficiency requirements for docketing a petition for rulemaking under 
10 CFR 2.803. The NRC is examining the issues raised in PRM-50-120 to 
determine whether these issues should be considered in rulemaking and 
is requesting public comment on this petition at this time.

    Dated at Rockville, Maryland, this 13th day of November 2019.

    For the Nuclear Regulatory Commission.
Annette L. Vietti-Cook,
Secretary of the Commission.
[FR Doc. 2019-24936 Filed 11-18-19; 8:45 am]
 BILLING CODE 7590-01-P
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