ML22024A172

From kanterella
Jump to navigation Jump to search
Draft NRC Regulatory Issues Summary 2014-06, Revision 1, Consideration of Current Operating Issues and Licensing Actions in License Renewal
ML22024A172
Person / Time
Issue date: 02/23/2023
From: Russell Felts
NRC/NRR/DNRL/NLRP
To:
James L
References
RIS-14-006, Rev. 1
Download: ML22024A172 (7)


See also: RIS 2014-06

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, DC 20555-0001

DRAFT NRC REGULATORY ISSUE SUMMARY 2014-06, REVISION 1,

CONSIDERATION OF CURRENT OPERATING ISSUES

AND LICENSING ACTIONS IN LICENSE RENEWAL

ADDRESSEES

All holders of, or applicants for, a power reactor operating license or construction permit under

Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of

Production and Utilization Facilities, except those that have certified that they have

permanently ceased operations and permanently removed all fuel from the reactor vessel.

All holders of, or applicants for, a power reactor early site permit or a combined license under

10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants.

INTENT

The U.S. Nuclear Regulatory Commission (NRC) is issuing this regulatory issue summary (RIS)

to provide information to applicants and licensees on how the NRC considers current operation

of the facility in the license renewal review under 10 CFR Part 54, Requirements for Renewal of

Operating Licenses for Nuclear Power Plants. This RIS requires no action or written response

on the part of any addressee.

BACKGROUND INFORMATION

In 10 CFR 54.21, Contents of applicationtechnical information, and 10 CFR 54.23, Contents

of applicationenvironmental information, the regulations identify the technical information that

must be submitted in a license renewal application (LRA) to enable the NRC staff to make a

determination that the license may be renewed, as identified in 10 CFR 54.29, Standards for

issuance of a renewed license. The license renewal review focuses on the management of

aging for structures and components within the scope of license renewal. To grant a renewed

license in accordance with 10 CFR 54.29, the NRC must find, in part, that the applicant has

demonstrated compliance with the current licensing basis (CLB) as follows:

(a) Actions have been identified and have been or will be taken with respect to

the matters identified in Paragraphs (a)(1) and (a)(2) of this section, such that

there is reasonable assurance that the activities authorized by the renewed

license will continue to be conducted in accordance with the CLB, and that any

changes made to the plants CLB in order to comply with this paragraph are in

accord with the Act and the Commissions regulations. These matters are:

(1) managing the effects of aging during the period of extended operation on the

functionality of structures and components that have been identified to require

review under § 54.21(a)(1); and

ML22024A172

RIS 2014-06, Rev. 1

Page 2 of 6

(2) time-limited aging analyses that have been identified to require review under

§ 54.21(c).

Licensing actions and current operating issues may arise during the review of either initial or

subsequent LRAs that may affect aspects of the review. For example, during the NRC staffs

review of an LRA, separate licensing actions, other CLB changes, and operating experience

have challenged the NRC staffs ability to conclude that the applicant has demonstrated it will

adequately manage the effects of aging. Whether these issues need to be considered in the

license renewal review depends on the effect that the information will have on the required

finding of 10 CFR 54.29(a) in regard to the adequacy of aging management for structures and

components and the applicants evaluation of time-limited aging analyses (TLAAs).

SUMMARY OF ISSUE

As required by 10 CFR 54.21(b), license renewal applicants need to update their applications

with newly-developed information that could impact aging management of structures and

components. Newly-identified information related to a current operating license issue or CLB

change(s) include the following examples:

the LRA

  • a current operating issue that potentially challenges the adequacy of the applicants

aging management programs (AMPs)

  • recent operating experience (that occurred between the operating experience review

cutoff date and the submission of the LRA) or late-breaking operating experience (that

arose during the LRA review) that potentially challenges the adequacy of the applicants

AMPs

These examples highlight some issues that may affect the NRC staffs license renewal review.

Addressing these and similar issues may require more resources from the applicant and the

NRC staff, potentially delaying the license renewal review schedule.

The above considerations pertain to current operating license holders. In addition, although

current combined license holders have yet to commence operation, the information in this RIS

may be useful to help them develop and implement operational programs that would facilitate

eventual license renewal.

1. Issues affecting the scope of license renewal

The applicants determination of systems, structures, and components (SSCs) within the scope

of license renewal must be based on the CLB. Significant changes to the CLB that occur during

the license renewal review present challenges because the CLB, and thus the scope of license

renewal, may be in flux. Such changes can arise from other licensing actions that are processed

concurrently with the LRA. To comply with 10 CFR 54.21(a), license renewal applicants must

ensure the license renewal scope reflects their current CLB.

These challenges are highlighted when an applicant submits its LRA concurrent with other

major licensing actions. For example, an applicants implementation of an NRC-approved

RIS 2014-06, Rev. 1

Page 3 of 6

extended power uprate can affect multiple areas of the CLB, such as the reactor vessel

internals and calculations for neutron fluence, upper shelf energy, and pressure-temperature

limits. The changes to such areas of the CLB also can result in significant modifications to major

balance-of-plant equipment.

When the review of these types of major licensing actions occurs concurrently with the license

renewal review, applicants should give extra consideration to the possibility of significant

changes to the CLB that could materially affect the LRA. Such changes may necessitate new

AMPs and TLAAs or may introduce new and significant aging effects and mechanisms that

could result in the addition of multiple aging management review line items to the LRA.

Examples of CLB changes that potentially are not significant such that the LRA would not be

materially affected could involve SSCs that are removed from the scope of license renewal or

SSCs that were added in scope but are already accounted for by existing aging management

activities in the LRA. Regardless of the significance of the impact to the LRA, the NRC staff

must review all such CLB changes before it can make the finding required by 10 CFR 54.29(a).

Therefore, LRA reviews that occur concurrently with licensing action reviews or other CLB

changes may require extra consideration, resources, and review time, including reviews held in

abeyance pending final determination of the impact of the CLB change on the LRA.

How significant changes to the CLB may affect the license renewal review depends on when the

CLB change is made. Figure 1 below shows four scenarios of CLB changes, labeled A through

D, and their relationship to the license renewal review. Scenario A marks a CLB change that

occurs before the LRA is submitted. Scenario B marks a CLB change that occurs before the last

required LRA update. Scenario C marks a CLB change that occurs after the last required LRA

update but before the renewed license decision. Scenario D marks a CLB change that occurs

after issuance of the renewed license.

Last Required LRA Renewed License

LRA Receipt Update Issued

A B C D

Figure 1 CLB change and LRA review timeline

Scenario A. If the CLB change is implemented before the LRA receipt, the LRA should reflect

the applicable CLB changes before submission, in accordance with the requirements of

10 CFR 54.21(a), (c), and (d), and 10 CFR 54.22, Contents of applicationtechnical

specifications.

Scenario B. CLB changes are reported pursuant to 10 CFR 54.21(b). As stated in

10 CFR 54.21(b), license renewal applicants must amend the LRA annually, to identify any CLB

changes that materially affect the contents of the LRA, including the [final safety analysis report]

supplement. The last annual update to the LRA that the applicant is required to submit is at

least 3 months before the scheduled completion of the NRC review. This update must capture

all CLB changes up to that point that materially affect the contents of the LRA in accordance

with 10 CFR 54.21(b). The NRC staff will evaluate these CLB changes for significance and

RIS 2014-06, Rev. 1

Page 4 of 6

therefore may need additional time to make the finding required by 10 CFR 54.29(a). The NRC

staff will issue its safety evaluation report when all open items have been closed, including any

open items associated with the reported CLB changes.

Scenario C. If the CLB change is implemented after the last required LRA update but before the

renewed license decision, the NRC staff will still evaluate the CLB changes that materially affect

the LRA for significance. The NRC staff will review these changes to determine whether they

affect the finding required by 10 CFR 54.29(a). If there is an impact to this finding, the NRC staff

may extend the review schedule to evaluate the CLB changes and their effects on aging

management and TLAAs before making its 10 CFR 54.29(a) finding.

Scenario D. CLB changes that occur after the renewed license is issued are addressed by Part

50 requirements (e.g., 50.59, 50.90) and may also be subject to the 10 CFR 54.37(b) reporting

requirements. RIS 2007-16, Revision 1, Implementation of the Requirements of

10 CFR 54.37(b) for Holders of Renewed Licenses, dated April 28, 2010 (Agencywide

Documents Access and Management System (ADAMS) Accession No. ML100250279),

provides additional information on these post-renewal reporting requirements.

2. Operating experience that occurs after the development of the application or during the

license renewal application review

As discussed in NUREG-2192, Revision 0, Standard Review Plan for Review of Subsequent

License Renewal Applications for Nuclear Power Plants, Appendix A.4, issued July 2017

(ADAMS Accession No. ML17188A158) for subsequent license renewal (for plant operation

from 60 to 80 years) and in LR-ISG-2011-05, Ongoing Review of Operating Experience, for

license renewal (for plant operation from 40 to 60 years) issued March 2012 (ADAMS Accession

No. ML12044A215), operating experience is a crucial aspect of any efforts to effectively

manage aging effects. Operating experience provides support for all other aspects of effective

AMPs and, as a continuous feedback mechanism, is used to identify AMP changes that are

necessary to maintain the overall effectiveness of the AMP. Operating experience can provide

objective evidence to support the conclusion that the effects of aging are managed adequately

so that the intended function(s) of structures and components will be maintained during the

period of extended operation. Pursuant to 10 CFR 54.21(a)(3), a license renewal applicant is

required to demonstrate that the effects of aging on structures and components subject to an

aging management review are adequately managed so that their intended function(s) will be

maintained consistent with the CLB for the period of extended operation.

The NRC staff acknowledges and understands that applicants must set a cutoff date for the

review of operating experience in order to complete and submit their applications for the staffs

review. However, recent (between the operating experience review cutoff date and the

submission of the LRA) or late-breaking (during the LRA review), operating experience could

affect an applicants ability to define its aging management activities and thus affect the staffs

ability to reach a regulatory decision under 10 CFR 54.29(a). For example, if a new aging

mechanism is identified during the LRA review, such as a corrosion mechanism that could

compromise the pressure boundary of a piping component subject to an aging management

review, the applicant must determine whether the proposed inspection techniques and

inspection frequencies are capable of identifying loss of material prior to a loss of intended

function. This may result in the applicant augmenting the specific aging management program,

or developing a new plant specific AMP, to demonstrate that the effects of aging will be

adequately managed.

RIS 2014-06, Rev. 1

Page 5 of 6

To make the finding required by 10 CFR 54.29(a), the NRC staff needs to receive information

about recent and late-breaking operating experience, if it materially affects an AMP, to have

sufficient technical basis to evaluate the adequacy of the applicants aging management

activities. License renewal applicants should inform the staff in a timely manner of recent or late-

breaking operating experience using appropriate communication vehicles, including voluntary

supplements to the application and the annual update required by 10 CFR 54.21(b), as

delineated above. The NRC will evaluate the recent and late-breaking operating experience for

impacts to the adequacy of the applicants AMPs and, therefore, may need additional

information and time to determine whether the finding required by 10 CFR 54.29(a) may be

made.

BACKFITTING AND ISSUE FINALITY DISCUSSION

This RIS provides information that clarifies how a licensing action or current operating issue that

is identified during a license renewal review may affect the NRCs determination on license

renewal. This RIS requires no action or written response. Therefore, the RIS does not contain a

new or changed NRC staff position or an interpretation of the regulations that would constitute

backfitting as defined in 10 CFR 50.109, Backfitting, or represent an inconsistency with

applicable issue finality provisions in 10 CFR Part 52.

FEDERAL REGISTER NOTIFICATION

The NRC will publish a notice of opportunity for public comment on this draft RIS in the Federal

Register.

CONGRESSIONAL REVIEW ACT

This RIS is not a rule as defined in the Congressional Review Act (5 U.S.C. §§ 801-808).

PAPERWORK REDUCTION ACT STATEMENT

This RIS does not contain new or amended information collection requirements that are subject

to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were

approved by the Office of Management and Budget (OMB), approval number 3150-0155.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, a collection

of information unless the document requesting or requiring the collection displays a currently

valid OMB control number.

RIS 2014-06, Rev. 1

Page 6 of 6

CONTACT

Please direct any questions about this matter to the technical contact listed below.

Russell Felts, Director

Division of Reactor Oversight

Office of Nuclear Reactor Regulation

Lead Project Manager: Christopher Tyree, NRR

301-415-3754

Email: Christopher.Tyree@nrc.gov

Note: NRC generic communications may be found on the NRC public website,

http://www.nrc.gov, under NRC Library/Document Collections.

ML22024A172 *via e-concurrence L-2021-GEN-0005

OFFICE PM:NLRP:DNRL Tech Editor BC:NLRP:DNRL D:DNRL OCIO OE

NAME CTyree Azariah-Kribbs LGibson BSmith DCullison JPeralta

DATE 11/21/2022 7/08/2022 11/17/2022 11/21/2022 1/18/2023 12/7/2022

OFFICE OGC LA:IOEB:DRO PM:IOEB:DRO BC:IOEB:DRO D:DRO:NRR

NAME STurk IBetts BBenney LRegner RFelts

DATE 1/17/2023 2/2/20233 2/13/2023 2/10/2023 2/23/2023