ML083500028

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Draft NRC Regulatory Issue Summary 2007-16, Rev. 1: Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses
ML083500028
Person / Time
Issue date: 03/18/2009
From: Mcginty T
Division of Policy and Rulemaking
To:
Homiack, M, NRR/DLR/RLRB 415-1683
Shared Package
ml082180410 List:
References
RIS-07-016, Rev. 1
Download: ML083500028 (6)


See also: RIS 2007-16

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, DC 20555-0001

Month XX, 2009

NRC REGULATORY ISSUE SUMMARY 2007-16, REV. 1

IMPLEMENTATION OF THE REQUIREMENTS OF

10 CFR 54.37(b) FOR HOLDERS OF RENEWED LICENSES

ADDRESSEES

All holders of operating licenses for nuclear power reactors, except those who have

permanently ceased operations and have certified that fuel has been permanently removed

from the reactor vessel.

INTENT

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

summary (RIS) to clarify guidance for stakeholders on implementing the requirements of

Title 10, Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants,

of the Code of Federal Regulations (10 CFR Part 54), specifically Section 54.37(b). This

revised RIS also addresses the applicability of Section 50.109, Backfitting, of 10 CFR Part 50,

Domestic Licensing of Production and Utilization Facilities.

BACKGROUND INFORMATION

On May 8, 1995, the NRC published an amendment to 10 CFR Part 54 (the License Renewal

Rule) in 60 Federal Register (FR) 22461-22495. In the amended rule, 10 CFR 54.21(d)

requires an applicant to include in its license renewal application (LRA) a supplement to its final

safety analysis report (FSAR) that contains a summary description of the programs and

activities credited for managing the effects of aging and the evaluation of time-limited aging

analyses (TLAAs). The existing regulatory process, existing licensee oversight activities, and

the additional regulatory controls associated with placing a summary description of aging

management activities in the FSAR provide assurance that the licensee will appropriately review

changes that could decrease the overall effectiveness of programs to manage the effects of

aging or the evaluation of TLAAs. In 10 CFR 54.37(b), the NRC requires the following:

After the renewed license is issued, the FSAR update required by

10 CFR 50.71(e) must include any systems, structures, and components newly

identified that would have been subject to an aging management review or

evaluation of time-limited aging analyses in accordance with § 54.21. This FSAR

update must describe how the effects of aging will be managed such that the

ML083500028

RIS 2007-16, Rev. 1

Page 2 of 5

intended function(s) in § 54.4(b) will be effectively maintained during the period of

extended operation.

The application of this regulatory requirement and the applicability of 10 CFR 50.109 (the

Backfit Rule) have been the subject of several interactions between the NRC staff and the

industry. Since issuing the amended License Renewal Rule, the Commissions position

remains that the Backfit Rule does not apply to the requirement in 10 CFR 54.37(b) to include

newly identified systems, structures, and components (SSCs) in the FSAR update required by

10 CFR 50.71(e)1. However, once a renewed license is issued, the Backfit Rule applies when

the NRC seeks to impose changes affecting aging management reviews or TLAA evaluations

previously reviewed and approved as part of the issuance of the renewed license.

The NRC staff addressed this issue in the original RIS2. However, while addressing

recommendations from the NRCs Office of the Inspector General (OIG) audit of the

effectiveness of the license renewal program, as documented in OIG-07-A-15, Audit of the

NRCs License Renewal Program, dated September 6, 2007 (ADAMS Accession

No. ML072490486), the NRC staff identified the need for a revised RIS. Specifically, OIG

suggested the following:

Establish a review process to determine whether or not Interim Staff Guidance meets the

provisions of 10 CFR 54.37(b), and document accordingly.

This revised RIS clarifies the requirements of the License Renewal Rule and the role of the

license renewal interim staff guidance (LR-ISG) process for including newly identified SSCs

under 10 CFR 54.37(b).

SUMMARY OF ISSUE

Newly Identified Systems, Structures, and Components

The intent of 10 CFR 54.37(b) is to capture those SSCs that, if they had been identified at the

time of the LRA, would have been subject to an aging management review or evaluation of

TLAAs. Therefore, 10 CFR 54.37(b) applies only to newly identified SSCs (hardware) and not

to licensee programs or procedures. In the context of 10 CFR 54.37(b), newly identified SSCs

to be included in the FSAR update required by 10 CFR 50.71(e) are those SSCs that meet

either of the following two conditions:

(1) The licensee installed the SSCs in the plant after the NRC granted a renewed operating

license, and the SSCs would have been included within the scope of license renewal

had they been installed before the NRC issued the renewed license.

(2) The SSCs existed in the plant when the NRC issued a renewed operating license and

were excluded from the scope of license renewal. However, after the issuance of the

1

The Commission re-affirmed this policy in a memorandum from Dale E. Klein to Hubert T. Bell, Response to

Recommendation 8 of 9/6/07 Audit Report on NRCs License Renewal Program, dated April 1, 2008

(ML080870286).

2

The NRC issued the original version of RIS 2007-16, "Implementation of the Requirements of 10 CFR 54.37(b) for

Holders of Renewed Licenses, on August 23, 2007 (ML071080338).

RIS 2007-16, Rev. 1

Page 3 of 5

renewed license, the SSCs are the subject of a current licensing basis change such that

the SSCs would have been considered within the scope of license renewal had the

change occurred before the NRC issued the renewed license.

If the SSCs meet one of these conditions, then the renewed license holder must include the

required information on aging management programs for those SSCs in the FSAR update. This

does not constitute backfitting under 10 CFR 50.109.

The requirement in 10 CFR 54.37(b) does not apply to those SSCs that existed in the plant

when the NRC originally granted the renewed operating license. For those SSCs, the NRC staff

position constitutes backfitting if:

(1) The NRC required the SSCs to be within the scope of the license renewal when it

granted the renewed operating license; however, because of an omission or mistake of

fact, (a) the licensee did not include the SSCs in the LRA, and (b) the NRC, in its review,

did not require the licensee to address the SSCs to meet the license renewal

requirements in effect during the review of the application.

(2) Based on the renewal requirements in effect, the NRC did not require the licensee to

include the SSCs within the scope of license renewal when the NRC granted the

renewed operating license; however, since issuance of the renewed operating license,

new information would have caused the SSCs to be included within the scope of license

renewal had the NRC known about the new information before it issued the renewed

license.

If one of these two conditions applies, the NRC staff position constitutes backfitting under

10 CFR 50.109(a)(4). Accordingly, to satisfy the requirements of 10 CFR 50.109, the NRC staff

must prepare either a documented evaluation demonstrating that one or more of the exceptions

in 10 CFR 50.109(a)(4)(i)-(iii) apply or a backfit analysis concluding that there is a cost-justified

substantial increase in the protection of public health and safety or in common defense and

security.

Identification of Systems, Structures, and Components under 10 CFR 54.37(b)

The language of 10 CFR 54.37(b) does not limit how newly identified SSCs are to be found. A

licensee is required to identify those SSCs that would have been subject to an aging

management review or evaluation of TLAAs in accordance with 10 CFR 54.21, Contents of

Application-Technical Information, and describe in the FSAR update required by

10 CFR 50.71(e) how the effects of aging will be managed such that the intended function(s) in

10 CFR 54.4(b) will be effectively maintained during the period of extended operation. One way

to identify these SSCs is through the LR-ISG process. This process develops and

communicates lessons learned during LRA reviews. The agency developed this process in

coordination with stakeholders and recently issued a revision, License Renewal Interim Staff

Guidance Process, Revision 1 (ADAMS Accession No. ML083500028), which expands the

evaluation and documentation of newly identified SSCs.

The NRC staff may discover new SSCs and issue generic information about them to

stakeholders through, for example, an LR-ISG or generic communication. Renewed license

holders should determine whether NRC-communicated information on newly identified SSCs

RIS 2007-16, Rev. 1

Page 4 of 5

applies to their facilities and, if appropriate, act to ensure compliance with the requirements of

10 CFR 54.37(b).

Final Safety Analysis Report Update Requirements

The FSAR update required by 10 CFR 54.37(b) must include newly identified SSCs that would

have been subject to an aging management review or evaluation as TLAAs in accordance with

10 CFR 54.21. The FSAR update must describe how the effects of aging will be managed such

that the intended function(s) in 10 CFR 54.4(b) will be maintained effectively during the period of

extended operation. In accordance with 10 CFR 50.71(e)(4), licensees must file FSAR updates

annually or 6 months after each refueling outage provided the interval between successive

updates does not exceed 24 months. The revisions must reflect all changes up to a maximum

of 6 months prior to the date of filing.

When issuing the amended License Renewal Rule, the Commission stressed the importance of

describing the aging management reviews or TLAAs for newly identified SSCs in the FSAR

(60 FR 22483-22484). It was noted in the FR notice that, because such a level of detail

appeared to be at odds with the requirement in 10 CFR 54.21(d), the FSAR supplement need

contain only a summary description of the aging management programs or TLAAs. However,

the Commission explained that for those SSCs subject to an aging management review as part

of the license renewal process, the application itself and the FSAR supplement together

provided the requisite regulatory control to ensure the efficacy of the aging management

program. Newly identified SSCs have not been subjected to the same level of review. Thus,

the level of detail required describing the aging management reviews or TLAAs in the FSAR

update for newly identified SSCs is appropriate even though it is greater than the level of detail

required for the original license renewal FSAR supplement.

BACKFIT DISCUSSION

This revised RIS provides regulatory clarification and does not represent a new or different NRC

staff position on the implementation of 10 CFR 54.37(b). It does not create or impose any new

or different applicable NRC staff positions inconsistent with the License Renewal Rule, as

amended. It requires no action or written response beyond what is required in 10 CFR 54.37(b).

Any action addressees take to implement changes to their reporting procedures in accordance

with the clarifications in this revised RIS is strictly voluntary; ensures compliance with current

regulations; and, therefore, is not a backfit under 10 CFR 50.109. This revised RIS clarifies the

requirements of the License Renewal Rule. Consequently, the NRC staff did not perform a

backfit analysis.

FEDERAL REGISTER NOTIFICATION

To be done after the public comment period. The revised RIS is informational and pertains to

an NRC staff position that does not depart from current regulatory requirements and practices.

RIS 2007-16, Rev. 1

Page 5 of 5

CONGRESSIONAL REVIEW ACT

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

and, therefore, is not subject to the Act.

PAPERWORK REDUCTION ACT STATEMENT

This RIS does not contain any information collections and, therefore, is not subject to the

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

PUBLIC PROTECTION NOTIFICATION

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

information or an information collection requirement unless the requesting document displays a

currently valid OMB control number.

CONTACT

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

appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

Timothy J. McGinty, Director

Division of Policy and Rulemaking

Office of Nuclear Reactor Regulation

Technical Contact: Matthew Homiack, NRR

301-415-1683

e-mail: Matthew.Homiack@nrc.gov

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

http://www.nrc.gov, under Electronic Reading Room/Document Collections.

ML083500028

OFFICE PM:RPOB:DLR TechEditor* BC:RPOB:DLR D:DLR

NAME MHomiack KAzariah-Kribbs TTate BHolian

DATE 318/2009 12/18/2008 3/18/2009 3/18/2009

OFFICE OGC (NLO) OGC (CRA) OIS

NAME GMizuno SCrockett GTrussell

DATE 3/11/2009 3/13/2009 2/26/2009

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