ML24164A211

FRN: General Notice. Level 3 Probabilistic Risk Assessment Project Documentation (Volume 7)

ML24164A211
Person / Time
Issue date:	07/08/2024
From:	Jonathan Evans NRC/RES/DRA/PRAB
To:
References
NRC-2024-0116, 07192024, 89FR58805
Download: ML24164A211 (5)

Text

[7590-01-P]

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.

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: Stacy.Schumann@nrc.gov. 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: Alan.Kuritzky@nrc.gov.

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.

• NRCs 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 NRCs Public Document Room (P DR) reference staff at 1-800-397-4209, at

301-415-4737, or by email to PDR.Resource@nrc.gov. For the convenience of the

reader, instructions about obtaining materials referenced in this document are provided

in the Availability of Documents section.

• NRCs 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 PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-

2 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 identif ying or contact information that you

do not want to be publicly disclosed in y our comment submission. The NRC will post all

comment submissions at https://www.regulat ions.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 w ant 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, Opti ons 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-

3 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 ma king and to help focus limited NRC resources

on issues most directly related to the agencys 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.

4 DOCUMENT DESCRIPTION ADAMS ACCESSION NO.

SRM-SECY-11-0089, Options for Proceeding ML112640419 with Future Level 3 Probabilistic Risk Assessment (PRA) Activities, dated September 21, 2011.

Level 3 PRA Project, Volume 7: Dry Cask ML24164A010 Storage PRA (Draft Report for Comment)

Dated: July 8, 2024.

For the Nuclear Regulatory Commission.

/RA/

Jonathan E. Evans, Chief, Probability Risk Assessment Branch, Division of Risk Analysis, Office of Nuclear Regulatory Research.

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