RIS 2007-16, U.S. Nuclear Regulatory Commission Regulatory Issue Summary of 2007-16. Revision 1: Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses: Difference between revisions

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{{Adams
{{Adams
| number = ML100250279
| number = ML071080338
| issue date = 04/28/2010
| issue date = 08/23/2007
| title = U.S. Nuclear Regulatory Commission Regulatory Issue Summary of 2007-16. Revision 1: Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses
| title = Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses
| author name = McGinty T J
| author name = Case M J
| author affiliation = NRC/NRR/DPR
| author affiliation = NRC/NRR/ADRO/DPR
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket = 05000219
| license number =  
| license number =  
| contact person = Homiack M, NRR/DLR, 415-1683
| contact person =  
| case reference number = FOIA/PA-2009-0070
| document report number = RIS-07-016
| document report number = RIS-07-016
| package number = ML100250250
| document type = NRC Regulatory Issue Summary
| document type = NRC Regulatory Issue Summary
| page count = 8
| page count = 7
}}
}}
{{#Wiki_filter:ML100250279 April 28, 2010 NRC REGULATORY ISSUE SUMMARY 2007-16, REVISION 1, IMPLEMENTATION OF THE REQUIREMENTS OF 10 CFR 54.37(b) FOR HOLDERS OF RENEWED LICENSES
See also: [[followed by::RIS 2007-16]]


==ADDRESSEES==
=Text=
All holders of operating licenses for nuclear power reactors under the provisions of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, "Domestic Licensing of Production and Utilization Facilities," except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vesse
{{#Wiki_filter:
[[Issue date::August 23, 2007]]


==INTENT==
NRC REGULATORY ISSUE SUMMARY 2007-16:IMPLEMENTATION OF THE REQUIREMENTS OF 10 CFR 54.37(b) FOR HOLDERS OF RENEWED LICENSESADDRESSEESAll holders of operating licenses for nuclear power reactors, except those who havepermanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.INTENTThe 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 informationrequired to be included in final safety analysis report (FSAR) updates.BACKGROUND INFORMATIONThe license renewal rule, 10 CFR Part 54, "Requirements for Renewal of Operating Licensesfor 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-
The U.S. Nuclear Regulatory Commission (NRC) is issuing this revised regulatory issue summary (RIS) to clarify guidance for holders of renewed licenses on implementing the requirements of 10 CFR 54.37(b), regarding newly identified systems, structures, and components (SSCs) and information required to be included in final safety analysis report (FSAR) update This revised RIS includes changes for consistency with the NRC's revised license renewal interim staff guidance (LR-ISG) process, issued on August 7, 2009, as LR-ISG-2007-01, "License Renewal Interim Staff Guidance Process, Revision 1." In part, the NRC staff issued a revised LR-ISG process to address a recommendation from the NRC's Office of the Inspector General (OIG) 2007 report, OIG-07-A-15, "Audit of the NRC's License Renewal Program." Under the revised process, the NRC staff evaluates each LR-ISG to determine whether it includes SSCs subject to the provisions of 10 CFR 54.37(b), and documentation of this determination is included in the LR-IS
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 license 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 §54.2 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 2007-16Page 2 of 6The 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 industr 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. ML06270023 DISCUSSIONNewly 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 thetime of the license renewal application, would have been subject to an aging management review or evaluation of TLAA 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 NRCapproved the license renewal application.-The SSCs would have been in the scope of license renewal based on the CLB change if10 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, inaccordance 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 arenot subject to the provisions of 10 CFR 54.37(b). Identification of SSCsThe language of 10 CFR 54.37(b) does not limit how or by whom newly identified SSCs are tobe foun A licensee may identify SSCs that should be within the scope of its license renewal program at any tim Currently, the only additional source that has identified new SSCs that should be in the scope of license renewal is the NRC's License Renewal Interim Staff Guidance(LR-ISG) proces 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 stakeholder RIS 2007-16Page 3 of 6There are two types of LR-ISGs-clarification and complianc Clarification LR-ISGs provideadditional 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 informatio Clarification LR-ISGs do not create new staff positions and do not apply to licensees holding renewed license Compliance LR-ISGs involve compliance with the regulations and, therefore, apply to both applicants and licensees holding renewed license 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 asto 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 RenewNuclear Power Plant Operating Licenses," Revision 1, September 2005*NUREG-1800, "Standard Review Plan for Review of License Renewal Applications forNuclear 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 of10 CFR Part 54-The License Renewal Rule," Revision 6, issued June 2005.The NRC issued the three following compliance LR-ISGs and subsequently incorporated theminto the referenced guidance documents:*Station Blackout SSCs-In LR-ISG-02, dated April 1, 2002 (ADAMS AccessionNo. 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 Holders-The NRC provided guidance on the identification and treatment ofelectrical 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 1.18 RIS 2007-16Page 4 of 6*Housings for Active Components-The NRC provided guidance on the identification andtreatment 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 renewalapplications as the process was evolvin 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 plant However, the agency issued some early renewed licenses without the licensees explicitly including the subject SSCs in the scope of their license renewal application Holdersof 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 FSA 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 Application-Technical Information," and should submit the information required by 10 CFR 54.37(b) in their next FSAR update.Future Notification of Newly Identified SSCsWith the level of experience that now exists with license renewal application reviews, the NRCstaff 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 license 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 UpdateThe FSAR update required by 10 CFR 54.37(b) must include newly identified SSCs that wouldhave been subject to an aging management review or evaluation as a TLAA in accordance with 10 CFR 54.2 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 theimportance 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 FR22483-22484)). 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 TLAA 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 progra Newly identified SSCs have not been subjected to the same level of revie 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 supplemen RIS 2007-16Page 5 of 6BACKFIT DISCUSSIONThis RIS does not involve a backfit under the backfit rule (10 CFR 50.109). The Commissionaddressed 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 proces The Commission does not intend to impose requirements on a licensee that go beyond what is necessary to adequately manage agin 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 applicatio Thus, requiring a licensee to consider newly identified SSCs after a renewed license is issued is not a backfi The requirements of 10 CFR 54.37(b) apply only to newly identified SSC They do not impose any changes in aging management programs or TLAAs after a renewed license is issued unrelated to a newly identified SS The backfit rule continues to apply to these types of changes.FEDERAL REGISTER NOTIFICATIONA notice of opportunity for public comment on this RIS was not published in the FederalRegister because the RIS is informational and pertains to a staff position that does not departfrom current regulatory requirements and practices.CONGRESSIONAL REVIEW ACTThis 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 STATEMENTThis Regulatory Issue Summary contains information collection requirements that are subject tothe 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 NotificationThe NRC may not conduct or sponsor, and a person is not required to respond to, a request forinformation or an information collection requirement unless the requesting document displays a currently valid OMB control numbe RIS 2007-16Page 6 of 6CONTACTPlease direct any questions about this matter to the technical contact listed below./RA by TQuay for/Michael J. Case, DirectorDivision of Policy and Rulemaking Office of Nuclear Reactor RegulationTechnical Contact:Stephen T. Hoffman, NRR301-415-3245 Email: sth@nrc.govNote: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collection RIS 2007-16Page 6 of 6CONTACTPlease direct any questions about this matter to the technical contact listed below./RA by TQuay for/Michael J. Case, DirectorDivision of Policy and Rulemaking Office of Nuclear Reactor RegulationTechnical Contact:Stephen T. Hoffman, NRR301-415-3245 Email: sth@nrc.govNote: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.DISTRIBUTION:RIS FileAccession No.: ML071080338OFFICEPM:RLRB:DLRTechEditorBC:RLRB:DLRD:DLRNAMESHoffmanHChangRAuluckPTKuo DATE05/15/0704/24/0705/16/0705/22/07 OFFICEBC:ITSB:DIRSD:DIRSD:DORLOE NAMETKobetzECollinsCHaneyDSolorio forCNolanDATE05/23/0705/30/0705/25/0706/06/07 OFFICEOGC (NLO)OGC (CRA)PMAS:NRROIS NAMEMZoblerSHamrickLHillMJanney DATE06/14/0705/31/0706/18/0706/26/07 OFFICELA:PGCB:DPRPGCB:DPRBC:PGCB:DPRD:DPR NAMECHawesAMarkleyMMurphyMCase DATE06/28/0706/27/0708/10/0708/23/07    OFFICIAL RECORD COPY
 
==BACKGROUND INFORMATION==
The license renewal rule in 10 CFR 54.21(d) requires that an applicant include in its license renewal application (LRA) 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 license In 10 CFR 54.37(b), the license renewal rule requires the following:
RIS 2007-16, Rev. 1 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 § 54.2 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 operatio The application of this regulatory requirement and the applicability of the backfit rule, 10 CFR 50.109, "Backfitting," have been the subject of several interactions between the NRC staff and the industr DISCUSSION 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 license renewal application, would have been subject to an aging management review or evaluation of TLAA 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 applicatio 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 SSC (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 licens 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 under 10 CFR 54.37(b) The language of 10 CFR 54.37(b) does not limit how or who finds newly identified SSC A licensee may identify SSCs that should be within the scope of its license renewal program at any tim The NRC staff may also discover newly identified SSC One way to identify these SSCs is through the LR-ISG proces Under this process, the NRC staff evaluates and documents its determinations as to whether an LR-ISG meets the provisions of 10 CFR 54.37(b) and the backfit rul If the NRC staff has determined that a final LR-ISG RIS 2007-16, Rev. 1 constitutes backfitting under 10 CFR 50.109, or communicates newly identified SSCs under the provisions of 10 CFR 54.37(b), then it will notify applicable renewed license holders as appropriate, for example by issuing site-specific letters or a generic communicatio As such, a renewed license holder should determine whether the final LR-ISG applies to its facility and, if appropriate, take actions to ensure compliance with the requirements of 10 CFR 54.37(b). The NRC issues LR-ISGs for various reasons, such as to (a) clarify which SSCs are to be included within the scope of license renewal under 10 CFR 54.4, (b) revise or clarify aging management recommendations in NUREG-1801, Revision 1, "Generic Aging Lessons Learned (GALL) Report," dated September 2005, or (c) address emergent issue As an example, in light of recent operating experience, the NRC developed draft LR-ISG-2009-01 to address aging management of certain spent fuel pool neutron-absorbing material While LR-ISGs may address a variety of license renewal issues, only certain LR-ISGs identify SSCs subject to the provisions of 10 CFR 54.37(b). To date, the NRC has issued three such LR-ISGs:
* Station Blackout SSCs-In LR-ISG-02, dated April 1, 2002 (Agencywide Documents Access and Management Systems (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 Section 2.5 of NUREG-1800, Revision 1, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants," dated September 2005 (SRP-LR).
* Electrical Fuse Holders-The 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 (a) SRP-LR Table 2.1-5 and Section 3.6, (b) Chapter VI and Section XI.E5 of the GALL Report, Volume 2, and (c) Appendix B to Nuclear Energy Institute (NEI) 95-10, Revision 6, "Industry Guidelines for Implementing the Requirements of 10 CFR Part 54-The License Renewal Rule," dated June 200 NEI 95-10 is endorsed by NRC Regulatory Guide 1.188, Revision 1, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses," dated September 200
* Housings for Active Components-The 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 NEI 95-10 Appendix The NRC identified the need for these LR-ISGs during the review of early LRAs as the process was evolvin 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 plant However, the agency issued some early renewed licenses without the licensees explicitly including the subject SSCs in the scope of their license renewal application Holders of renewed licenses should verify that their license renewal programs include these SSCs and that appropriate aging management programs exist and are described in the FSA Those licensees whose programs do not already include these SSCs must perform an aging management review or evaluation of TLAAs in accordance with 10 CFR 54.2 For these SSCs, the updated FSAR must contain a description of how the effects of aging will be managed such that the intended function(s) in RIS 2007-16, Rev. 1 10 CFR 54.4(b) will be effectively maintained during the period of extended operatio Development and implementation of aging management programs for newly identified SSCs under 10 CFR 54.37(b) are not considered backfit 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 54.2 The FSAR update needs to describe how the licensee will manage the effects of aging in order to effectively maintain the intended function(s) in 10 CFR 54.4(b) during the period of extended operatio 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)). The FR notice noted 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 TLAA 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 progra Newly identified SSCs have not been subjected to the same level of revie 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 supplemen NRC Verification The primary method the NRC uses to verify licensee implementation of the requirements of 10 CFR 54.37(b) is included in NRC Inspection Procedure 71003, "Post-Approval Site Inspection for License Renewal." One of the objectives of Inspection Procedure 71003 is to verify that newly identified SSCs, pursuant to 10 CFR 54.37(b) and this RIS, are implemented in accordance with 10 CFR Part 54, "Requirements for Renewal of Operating Licenses for Nuclear Power Plants."
 
==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 10 CFR Part 5 It requires no action or written response beyond what is required in 10 CFR 54.37(b).
 
===FEDERAL REGISTER NOTIFICATION===
A notice of opportunity for public comment on a draft revised RIS was published in the Federal Register (74 FR 13272) on March 26, 2009, for a 30-day comment perio The comment period was subsequently extended for an additional 30 days (74 FR 19109), in part, to facilitate RIS 2007-16, Rev. 1 discussions during a public meeting on April 29, 200 A summary for this meeting was issued on May 26, 2009 (ADAMS Accession No. ML091310269). Comments were received from the Nuclear Energy Institute by letter dated May 27, 2009 (ADAMS Accession No. ML091540208). The staff's evaluation of these comments is publicly available under ADAMS Accession No. ML10025031
 
===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 Ac
 
===PAPERWORK REDUCTION ACT STATEMENT===
This RIS does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control numbers 3150-0011 and 3150-015 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 Office of Management and Budget control numbe
 
==CONTACT==
Please direct any questions about this matter to the technical contact listed below, or to the appropriate Office of Nuclear Reactor Regulation (NRR) project manage /RA/
Timothy J. McGinty, Director Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
 
===Technical Contact:===
Matthew J. Homiack, NRR (301) 415-1683 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 Collection RIS 2007-16, Rev.
}}
}}
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Revision as of 01:20, 6 March 2018

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


See also: RIS 2007-16

Text

August 23, 2007

NRC REGULATORY ISSUE SUMMARY 2007-16:IMPLEMENTATION OF THE REQUIREMENTS OF 10 CFR 54.37(b) FOR HOLDERS OF RENEWED LICENSESADDRESSEESAll holders of operating licenses for nuclear power reactors, except those who havepermanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel.INTENTThe 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 informationrequired to be included in final safety analysis report (FSAR) updates.BACKGROUND INFORMATIONThe license renewal rule, 10 CFR Part 54, "Requirements for Renewal of Operating Licensesfor 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 license 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 §54.2 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 2007-16Page 2 of 6The 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 industr 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. ML06270023 DISCUSSIONNewly 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 thetime of the license renewal application, would have been subject to an aging management review or evaluation of TLAA 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 NRCapproved the license renewal application.-The SSCs would have been in the scope of license renewal based on the CLB change if10 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, inaccordance 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 arenot subject to the provisions of 10 CFR 54.37(b). Identification of SSCsThe language of 10 CFR 54.37(b) does not limit how or by whom newly identified SSCs are tobe foun A licensee may identify SSCs that should be within the scope of its license renewal program at any tim Currently, the only additional source that has identified new SSCs that should be in the scope of license renewal is the NRC's License Renewal Interim Staff Guidance(LR-ISG) proces 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 stakeholder RIS 2007-16Page 3 of 6There are two types of LR-ISGs-clarification and complianc Clarification LR-ISGs provideadditional 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 informatio Clarification LR-ISGs do not create new staff positions and do not apply to licensees holding renewed license Compliance LR-ISGs involve compliance with the regulations and, therefore, apply to both applicants and licensees holding renewed license 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 asto 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 RenewNuclear Power Plant Operating Licenses," Revision 1, September 2005*NUREG-1800, "Standard Review Plan for Review of License Renewal Applications forNuclear 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 of10 CFR Part 54-The License Renewal Rule," Revision 6, issued June 2005.The NRC issued the three following compliance LR-ISGs and subsequently incorporated theminto the referenced guidance documents:*Station Blackout SSCs-In LR-ISG-02, dated April 1, 2002 (ADAMS AccessionNo. 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 Holders-The NRC provided guidance on the identification and treatment ofelectrical 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 1.18 RIS 2007-16Page 4 of 6*Housings for Active Components-The NRC provided guidance on the identification andtreatment 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 renewalapplications as the process was evolvin 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 plant However, the agency issued some early renewed licenses without the licensees explicitly including the subject SSCs in the scope of their license renewal application Holdersof 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 FSA 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 Application-Technical Information," and should submit the information required by 10 CFR 54.37(b) in their next FSAR update.Future Notification of Newly Identified SSCsWith the level of experience that now exists with license renewal application reviews, the NRCstaff 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 license 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 UpdateThe FSAR update required by 10 CFR 54.37(b) must include newly identified SSCs that wouldhave been subject to an aging management review or evaluation as a TLAA in accordance with 10 CFR 54.2 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 theimportance 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 FR22483-22484)). 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 TLAA 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 progra Newly identified SSCs have not been subjected to the same level of revie 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 supplemen RIS 2007-16Page 5 of 6BACKFIT DISCUSSIONThis RIS does not involve a backfit under the backfit rule (10 CFR 50.109). The Commissionaddressed 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 proces The Commission does not intend to impose requirements on a licensee that go beyond what is necessary to adequately manage agin 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 applicatio Thus, requiring a licensee to consider newly identified SSCs after a renewed license is issued is not a backfi The requirements of 10 CFR 54.37(b) apply only to newly identified SSC They do not impose any changes in aging management programs or TLAAs after a renewed license is issued unrelated to a newly identified SS The backfit rule continues to apply to these types of changes.FEDERAL REGISTER NOTIFICATIONA notice of opportunity for public comment on this RIS was not published in the FederalRegister because the RIS is informational and pertains to a staff position that does not departfrom current regulatory requirements and practices.CONGRESSIONAL REVIEW ACTThis 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 STATEMENTThis Regulatory Issue Summary contains information collection requirements that are subject tothe 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 NotificationThe NRC may not conduct or sponsor, and a person is not required to respond to, a request forinformation or an information collection requirement unless the requesting document displays a currently valid OMB control numbe RIS 2007-16Page 6 of 6CONTACTPlease direct any questions about this matter to the technical contact listed below./RA by TQuay for/Michael J. Case, DirectorDivision of Policy and Rulemaking Office of Nuclear Reactor RegulationTechnical Contact:Stephen T. Hoffman, NRR301-415-3245 Email: sth@nrc.govNote: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collection RIS 2007-16Page 6 of 6CONTACTPlease direct any questions about this matter to the technical contact listed below./RA by TQuay for/Michael J. Case, DirectorDivision of Policy and Rulemaking Office of Nuclear Reactor RegulationTechnical Contact:Stephen T. Hoffman, NRR301-415-3245 Email: sth@nrc.govNote: NRC generic communications may be found on the NRC public Web site, http://www.nrc.gov, under Electronic Reading Room/Document Collections.DISTRIBUTION:RIS FileAccession No.: ML071080338OFFICEPM:RLRB:DLRTechEditorBC:RLRB:DLRD:DLRNAMESHoffmanHChangRAuluckPTKuo DATE05/15/0704/24/0705/16/0705/22/07 OFFICEBC:ITSB:DIRSD:DIRSD:DORLOE NAMETKobetzECollinsCHaneyDSolorio forCNolanDATE05/23/0705/30/0705/25/0706/06/07 OFFICEOGC (NLO)OGC (CRA)PMAS:NRROIS NAMEMZoblerSHamrickLHillMJanney DATE06/14/0705/31/0706/18/0706/26/07 OFFICELA:PGCB:DPRPGCB:DPRBC:PGCB:DPRD:DPR NAMECHawesAMarkleyMMurphyMCase DATE06/28/0706/27/0708/10/0708/23/07 OFFICIAL RECORD COPY