ML071080338

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Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses
ML071080338
Person / Time
Site: Oyster Creek
Issue date: 08/23/2007
From: Michael Case
NRC/NRR/ADRO/DPR
To:
References
FOIA/PA-2009-0070 RIS-07-016
Download: ML071080338 (7)


See also: RIS 2007-16

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR REACTOR REGULATION

WASHINGTON, D.C. 20555-0001

August 23, 2007

NRC REGULATORY ISSUE SUMMARY 2007-16:

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 regulatory issue summary (RIS)

to provide guidance to holders of renewed licenses on implementing the requirements of

Title 10 of the Code of Federal Regulations (10 CFR) Section 54.37(b), regarding information

required to be included in final safety analysis report (FSAR) updates.

BACKGROUND INFORMATION

The license renewal rule, 10 CFR Part 54, Requirements for Renewal of Operating Licenses

for Nuclear Power Plants, requires in 10 CFR 54.21(d) that an applicant include in its license

renewal application a supplement to its 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 changes that could

decrease the overall effectiveness of programs to manage the effects of aging or evaluation of

TLAAs receive appropriate review by the licensee. In 10 CFR 54.37(b), the license renewal rule

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 intended function(s) in §54.4(b) will be effectively

maintained during the period of extended operation.

ML071080338

RIS 2007-16

Page 2 of 6

The application of this regulatory requirement and the applicability of the backfit rule,

10 CFR 50.109, Backfitting, have been the subject of significant interactions between the

NRC staff and the industry. The most recent discussion of these interactions appears in an

October 11, 2006, letter from the NRC to the Nuclear Energy Institute (NEI) available in the

Agencywide Documents Access and Management System (ADAMS) under ADAMS Accession

No. ML062700236.

DISCUSSION

Newly Identified Systems, Structures, and Components (SSCs)

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

time of the license renewal application, would have been subject to an aging management

review or evaluation of TLAAs. In the context of 10 CFR 54.37(b), newly identified SSCs that

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

meet one of the two following conditions:

(1) There is a change to the current licensing basis (CLB) that meets the following criteria:

-

The change impacts SSCs that were not in scope for license renewal when the NRC

approved the license renewal application.

-

The SSCs would have been in the scope of license renewal based on the CLB change if

10 CFR 54.4(a) were applied to the SSCs.

(2) SSCs were installed in the plant at the time of the license renewal review that, in

accordance with the CLB at the time, should have been included in the scope of license

renewal per 10 CFR 54.4(a) but were not identified as in scope until after issuance of the

renewed license.

SSCs that are plant additions or modifications installed after the renewed license is issued are

not subject to the provisions of 10 CFR 54.37(b).

Identification of SSCs

The language of 10 CFR 54.37(b) does not limit how or by whom newly identified SSCs are to

be found. A licensee may identify SSCs that should be within the scope of its license renewal

program at any time. Currently, the only additional source that has identified new SSCs that

should be in the scope of license renewal is the NRCs License Renewal Interim Staff Guidance

(LR-ISG) process. The agency developed the LR-ISG process in coordination with the industry

and issued it in final form on December 12, 2003 (ADAMS Accession No. ML023520620). The

LR-ISG process captures lessons learned by the NRC and industry during license renewal

application reviews and communicates them in a timely manner to all stakeholders.

RIS 2007-16

Page 3 of 6

There are two types of LR-ISGsclarification and compliance. Clarification LR-ISGs provide

additional guidance to applicants that the staff or stakeholders feel is necessary to improve the

efficiency and effectiveness of the license renewal process or to help reduce the number of

requests for additional information. Clarification LR-ISGs do not create new staff positions and

do not apply to licensees holding renewed licenses. Compliance LR-ISGs involve compliance

with the regulations and, therefore, apply to both applicants and licensees holding renewed

licenses. As discussed later in this document under Backfit Discussion, the backfit rule,

10 CFR 50.109, does not apply to the requirement in 10 CFR 54.37(b) to include newly

identified SSCs in the FSAR update required by 10 CFR 50.71(e). The backfit rule would apply

to other changes after a renewed license is issued affecting aging management or TLAA

evaluations that do not involve the scope of the license renewal rule as defined under the

discussion of newly identified SSCs above.

The NRC staff previously indicated that it would notify licensees by generic communication as

to which LR-ISGs are related to compliance and involve newly identified SSCs after the

LR-ISGs were incorporated into the following license renewal guidance documents, as

applicable:

Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew

Nuclear Power Plant Operating Licenses, Revision 1, September 2005

NUREG-1800, Standard Review Plan for Review of License Renewal Applications for

Nuclear Power Plants (SRP-LR), Revision 1, September 2005

NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Volumes 1 and 2,

Revision 1, September 2005 (incorporated by reference in the SRP-LR)

RG 1.188 endorses NEI 95-10, Industry Guidelines for Implementing the Requirements of

10 CFR Part 54The License Renewal Rule, Revision 6, issued June 2005.

The NRC issued the three following compliance LR-ISGs and subsequently incorporated them

into the referenced guidance documents:

Station Blackout SSCsIn LR-ISG-02, dated April 1, 2002 (ADAMS Accession

No. ML020920464), the NRC provided additional guidance for identifying the SSCs relied

upon to meet the requirements of the station blackout rule (10 CFR 50.63, Loss of All

Alternating Current Power) as required by 10 CFR 54.4(a)(3). The guidance in this LR-ISG

was subsequently incorporated into SRP-LR, Section 2.5.

Electrical Fuse HoldersThe NRC provided guidance on the identification and treatment of

electrical fuse holders for license renewal in LR-ISG-05, dated March 10, 2003 (ADAMS

Accession No. ML030690492). The guidance in this LR-ISG was subsequently

incorporated into SRP-LR, Table 2.1-5 and Section 3.6, GALL Report, Chapter VI and

Aging Management Program XI.E5, and Appendix B to NEI 95-10 endorsed by RG 1.188.

RIS 2007-16

Page 4 of 6

Housings for Active ComponentsThe NRC provided guidance on the identification and

treatment of housing for active components for license renewal in LR-ISG-06, dated April 8,

2003 (ADAMS Accession No. ML031010423). The guidance in this LR-ISG was

subsequently incorporated into SRP-LR, Table 2.1-5 and Appendix B to NEI 95-10

endorsed by RG 1.188.

The NRC identified the need for these LR-ISGs during the review of early license renewal

applications as the process was evolving. As such, most holders of renewed licenses may

have already included the SSCs discussed in these LR-ISGs in the scope of renewal for their

plants. However, the agency issued some early renewed licenses without the licensees

explicitly including the subject SSCs in the scope of their license renewal applications. Holders

of renewed licenses should verify that their original license renewal programs included these

SSCs and that appropriate aging management programs exist and are described in the FSAR.

Those licensees whose programs do not already include these SSCs must perform an aging

management review in accordance with 10 CFR 54.21, Contents of ApplicationTechnical

Information, and should submit the information required by 10 CFR 54.37(b) in their next FSAR

update.

Future Notification of Newly Identified SSCs

With the level of experience that now exists with license renewal application reviews, the NRC

staff does not anticipate identifying on a generic basis new SSCs in the scope of license

renewal that require consideration under 10 CFR 54.37(b) by holders of renewed licenses. In

the event that new SSCs are identified that meet the definition above for newly identified SSCs

(e.g., in a future LR-ISG or guidance document update), the NRC staff will inform licensees of

the need to consider the SSCs for applicability to their facilities.

FSAR Update

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 a TLAA in accordance with

10 CFR 54.21. The FSAR update needs to 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.

When the NRC issued the amended license renewal rule in 1995, the Commission stressed the

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

the FSAR (Volume 60 of the Federal Register (FR), pages 22483-22484 (60 FR

22483-22484)). It was noted in the FR notice that such a level of detail appeared to be at odds

with the requirement in 10 CFR 54.21(d) that the FSAR supplement need only contain a

summary description of the aging management programs or TLAAs. However, the Commission

explained that for those SSCs that were 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 to describe 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.

RIS 2007-16

Page 5 of 6

BACKFIT DISCUSSION

This RIS does not involve a backfit under the backfit rule (10 CFR 50.109). The Commission

addressed the applicability of the backfit rule both when it promulgated the license renewal rule

in 1991 (56 FR 64974) and when amending it in 1995 (60 FR 22490-22491). In discussing

whether the backfit rule should apply to the review of a license renewal application, the

Commission stated that the agency may impose any additional requirements necessary to

manage the effects of aging without consideration of costs as part of the license renewal

process. The Commission does not intend to impose requirements on a licensee that go

beyond what is necessary to adequately manage aging. This position is analogous to the

compliance exception of 10 CFR 50.109(a)(4)(i). Newly identified SSCs would have been

subject to an aging management review if they had been identified at the time of the license

renewal application. Thus, requiring a licensee to consider newly identified SSCs after a

renewed license is issued is not a backfit. The requirements of 10 CFR 54.37(b) apply only to

newly identified SSCs. They do not impose any changes in aging management programs or

TLAAs after a renewed license is issued unrelated to a newly identified SSC. The backfit rule

continues to apply to these types of changes.

FEDERAL REGISTER NOTIFICATION

A notice of opportunity for public comment on this RIS was not published in the Federal

Register because the RIS is informational and pertains to a staff position that does not depart

from current regulatory requirements and practices.

CONGRESSIONAL REVIEW ACT

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

and, therefore, is not subject to the Act.

PAPERWORK REDUCTION ACT STATEMENT

This Regulatory Issue Summary contains information collection requirements that are subject to

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

were approved by the Office of Management and Budget (OMB), approval numbers 3150-0011

and 3150-0155.

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.

RIS 2007-16

Page 6 of 6

CONTACT

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

/RA by TQuay for/

Michael J. Case, Director

Division of Policy and Rulemaking

Office of Nuclear Reactor Regulation

Technical Contact:

Stephen T. Hoffman, NRR

301-415-3245

Email: sth@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.

RIS 2007-16

Page 6 of 6

CONTACT

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

/RA by TQuay for/

Michael J. Case, Director

Division of Policy and Rulemaking

Office of Nuclear Reactor Regulation

Technical Contact:

Stephen T. Hoffman, NRR

301-415-3245

Email: sth@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.

DISTRIBUTION:

RIS File

Accession No.: ML071080338

OFFICE

PM:RLRB:DLR

TechEditor

BC:RLRB:DLR

D:DLR

NAME

SHoffman

HChang

RAuluck

PTKuo

DATE

05/15/07

04/24/07

05/16/07

05/22/07

OFFICE

BC:ITSB:DIRS

D:DIRS

D:DORL

OE

NAME

TKobetz

ECollins

CHaney

DSolorio for

CNolan

DATE

05/23/07

05/30/07

05/25/07

06/06/07

OFFICE

OGC (NLO)

OGC (CRA)

PMAS:NRR

OIS

NAME

MZobler

SHamrick

LHill

MJanney

DATE

06/14/07

05/31/07

06/18/07

06/26/07

OFFICE

LA:PGCB:DPR

PGCB:DPR

BC:PGCB:DPR

D:DPR

NAME

CHawes

AMarkley

MMurphy

MCase

DATE

06/28/07

06/27/07

08/10/07

08/23/07

OFFICIAL RECORD COPY