[Federal Register Volume 89, Number 139 (Friday, July 19, 2024)]
[Notices]
[Pages 58805-58806]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-15251]



[[Page 58805]]

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NUCLEAR REGULATORY COMMISSION

[NRC-2024-0116]


Level 3 Probabilistic Risk Assessment Project Documentation 
(Volume 7)

AGENCY: Nuclear Regulatory Commission.

ACTION: Draft report; request for comment.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing for 
public comment a draft report on the Level 3 Probabilistic Risk 
Assessment (PRA) project; specifically, ``Volume 7: Dry Cask Storage 
PRA.''

DATES: Submit comments by September 17, 2024. Comments received after 
this date will be considered if it is practical to do so, but the 
Commission is able to ensure consideration only for comments received 
on or before this date.

ADDRESSES: You may submit comments by any of the following methods; 
however, the NRC encourages electronic comment submission through the 
Federal rulemaking website:
     Federal rulemaking website: Go to https://www.regulations.gov and search for Docket ID NRC-2024-0116. Address 
questions about Docket IDs in Regulations.gov to Stacy Schumann; 
telephone: 301-415-0624; email: [email protected]. For technical 
questions, contact the individual listed in the FOR FURTHER INFORMATION 
CONTACT section of this document.
     Mail comments to: Office of Administration, Mail Stop: 
TWFN-7-A60M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, ATTN: Program Management, Announcements and Editing Staff.
    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: Alan Kuritzky, Office of Nuclear 
Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001, telephone: 301-415-1552, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2024-0116 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-2024-0116.
     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, at 301-415-4737, 
or by email to [email protected]. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the ``Availability of Documents'' section.
     NRC's PDR: The PDR, where you may examine and order copies 
of publicly available documents, is open by appointment. To make an 
appointment to visit the PDR, please send an email to 
[email protected] or call 1-800-397-4209 or 301-415-4737, between 8 
a.m. and 4 p.m. eastern time (ET), Monday through Friday, except 
Federal holidays.

B. Submitting Comments

    The NRC encourages electronic comment submission through the 
Federal rulemaking website (https://www.regulations.gov). Please 
include Docket ID NRC-2024-0116 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. Discussion

    As directed in SRM-SECY-11-0089, ``Options for Proceeding with 
Future Level 3 Probabilistic Risk Assessment (PRA) Activities,'' the 
staff is conducting a full-scope multi-unit site Level 3 PRA (Level 3 
PRA project) that addresses all internal and external hazards; all 
plant operating modes; and all reactor units, spent fuel pools, and dry 
cask storage (DCS). The reference site for this study contains two 
four-loop Westinghouse pressurized water reactors with large dry 
containments. The objectives of the Level 3 PRA project are to (1) 
develop a Level 3 PRA, generally based on current state-of-practice 
methods, tools, and data, that (a) reflects technical advances since 
the last NRC-sponsored Level 3 PRAs (NUREG-1150), which were completed 
over 30 years ago, and (b) addresses scope considerations that were not 
previously considered (e.g., low-power and shutdown risk, multi-unit 
risk, other radiological sources); (2) extract new insights to enhance 
regulatory decision making and to help focus limited NRC resources on 
issues most directly related to the agency's mission to protect public 
health and safety; (3) enhance PRA staff capability and expertise and 
improve documentation practices to make PRA information more 
accessible, retrievable, and understandable; and (4) demonstrate 
technical feasibility and evaluate the realistic cost of developing new 
Level 3 PRAs.
    The work performed under this project is being documented as a 
multi-volume report. The current Level 3 PRA project report (Volume 7) 
describes the analyses and results for the DCS PRA. The Level 3 PRA 
project DCS PRA is a site-specific and cask-specific analysis that 
consists of the following interrelated technical elements: initiating 
event analysis, structural analysis, thermal analysis, human 
reliability analysis, multipurpose canister failure analysis, systems 
analysis, consequence analysis, and risk results quantification. The 
study predicted that there would be no prompt fatalities from DCS 
within 10 miles of the site. Results are reported for several other 
consequence metrics, including individual latent cancer fatality risk, 
total latent cancer fatality cases, population dose from 0-50 miles and 
0-100 miles, economic cost, and population affected by intermediate 
phase relocation. Regardless of the consequence metric, the risk from 
DCS operations was calculated to be very low.

III. Availability of Documents

    The documents identified in the following table are available to 
interested persons through ADAMS, as indicated.

[[Page 58806]]



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                                                        ADAMS accession
                 Document description                         No.
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SRM-SECY-11-0089, ``Options for Proceeding with              ML112640419
 Future Level 3 Probabilistic Risk Assessment (PRA)
 Activities,'' dated September 21, 2011..............
Level 3 PRA Project, Volume 7: Dry Cask Storage PRA          ML24164A010
 (Draft Report for Comment)..........................
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    Dated: July 8, 2024.

    For the Nuclear Regulatory Commission.
Jonathan Evans,
Chief, Probability Risk Assessment Branch, Division of Risk Analysis, 
Office of Nuclear Regulatory Research.
[FR Doc. 2024-15251 Filed 7-18-24; 8:45 am]
BILLING CODE 7590-01-P