ML091660539

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Regulatory Issue Summary 2009-xx Inservice Inspection and Testing Requirements of Dynamic Restraints (Snubbers)
ML091660539
Person / Time
Issue date: 11/25/2009
From: Mcginty T, Mchale J
NRC/NRR/DCI/CPTB
To:
Gurjendra S. Bedi, DCI/CPTB, 415-1393
References
Download: ML091660539 (6)


Text

ML091660539 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001

[Month, Day], 2009 NRC REGULATORY ISSUE

SUMMARY

2009-xx INSERVICE INSPECTION AND TESTING REQUIREMENTS OF DYNAMIC RESTRAINTS (SNUBBERS)

ADDRESSEES 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 vessel.

All holders of, and applicants for, nuclear power plant construction permits, early site permits, and limited work authorizations for nuclear power reactors under the provisions of 10 CFR Part 50.

INTENT The U.S. Nuclear Regulatory Commission (NRC or Commission) is issuing this regulatory issue summary (RIS) to remind licensees of the requirements for the inservice inspection (ISI) and testing of dynamic restraints (snubbers) under 10 CFR 50.55a(g) and 10 CFR 50.55a(b)(3)(v).

This RIS requires no action or written response on the part of an addressee.

BACKGROUND INFORMATION The regulations at 10 CFR 50.55a(b) detail the Codes and standards that have been approved for inclusion in 10 CFR Part 50, including the effective edition and addenda of the American Society of Mechanical Engineer (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code).

The regulations at 10 CFR 50.55a(g) establish the ISI requirements that licensees must use when performing ISI of components (including supports). 10 CFR 50.55a(g)(4) states, Throughout the service life of a boiling or pressurized water-cooled nuclear power facility, components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of editions of the ASME BPV Code and addenda. ASME Section XI provides the rules for ISI of nuclear power plant components.

The regulation at 10 CFR 50.55a(g)(4)(ii) requires the use of the latest edition and addenda of the Code that has been incorporated by reference 12 months prior to the beginning of each 120-month inspection interval. This Code is considered the Code of Record for the inspection interval.

RIS 2009-XX Page 2 of 5 The regulation at 10 CFR 50.55a(g)(4)(iv) states that ISI of components (including supports) may meet the requirements set forth in subsequent editions to the Code of Record and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to limitations and modifications listed in 10 CFR 50.55a(b) and subject to Commission approval.

The regulations at 10 CFR 50.55a(g) require ISI of components (including supports) without specifically mentioning snubbers. Consequently, confusion resulted and some licensees mistakenly believed that ISI and testing of snubbers is not a regulatory requirement. The NRC clarified, in the final rule dated September 22, 1999, [(Volume 64 of the Federal Register, pages 51370, 51388-89 (64 FR 51370, 51388-89)], that testing of snubbers is a regulatory requirement and has been for many years.

The regulations at 10 CFR 50.55a(g)(4) require that ASME Code Class 1, 2, and 3 components (including supports) meet the ISI requirements of ASME Code Section XI. Article IWF-5000, Inservice Inspection Requirements for Snubbers, of ASME Code Section XI provides requirements for the examination and testing of snubbers in nuclear power plants. Therefore, inservice examination and testing of snubbers are required by 10 CFR 50.55a because it incorporates by reference ASME Section XI requirements, including Article IWF-5000.

Article IWF-5000 has required the ISI and testing of snubbers since the first issuance of Subsection IWF in the Winter 1978 Addenda of ASME Section XI, which was incorporated in 10 CFR 50.55a in January 1982. Before ASME Section XI incorporated snubber examination and testing requirements, licensees used snubber examination and testing requirements as defined in their plants TS.

Improved Standard TS for various boiling and pressurized water-cooled nuclear power plants (NUREG-1430 thru 1434, Revision 3, published in June 2004) allow relocating inservice examination and testing requirements of snubbers from the TS to a plants Technical Requirements Manual (TRM). However, relocating snubber ISI and testing requirements from the TS to TRM does not eliminate the need to comply with the 10 CFR 50.55a requirements.

For plants using their TS to govern ISI and testing of snubbers, 10 CFR 50.55a (g)(5)(ii) requires that if a revised ISI program for a facility conflicts with the TS, the licensee shall apply to the Commission for amendment of the TS to conform the TS to the revised program. Therefore, when performing 120-month ISI program updates in accordance with 10 CFR 50.55a (g)(4),

licensees must submit any required amendments to ensure their TS remain consistent with the new code of record or NRC-approved alternative used in lieu of the Code requirements. The TS governing the snubber ISI and test program do not eliminate the 10 CFR50.55a requirements to update the program at 120-month intervals or to request and receive NRC authorization for alternatives to the Code requirements when appropriate.

The 2004 edition of ASME Section XI and the ASME OM Code are incorporated in 10 CFR 50.55a (Industry Codes and Standards; Amended Requirements, 73 FR 52730; September 10, 2008). Article IWF-5000 of the ASME BPV Code,Section XI, 2004 Edition, requires preservice and inservice examinations and testing of snubbers at nuclear power plants as part of the licensees ISI program in accordance with ASME/American National Standards Institute Standard for Operation and Maintenance of Nuclear Power Plants, Part 4 (OM-4), 1987 Edition with OMa-1988 Addenda.

RIS 2009-XX Page 3 of 5 The regulation at 10 CFR 50.55a(b)(3)(v) allows the optional use of Subsection ISTD, Preservice and Inservice Examination and Testing of Dynamic Restraint (Snubbers) in Light-Water Reactor Nuclear Power Plants, of the ASME OM Code-1995 Edition through the latest edition and addenda incorporated by reference in 10 CFR 50.55a(b)(3) in lieu of ASME Section XI, Articles IWF-5200(a) and (b) and IWF-5300(a) and (b) by making appropriate changes to TS or licensee-controlled documents. The regulation at 10 CFR 50.55a(b)(3)(v) also states, Preservice and inservice examination must be performed using the VT-3 visual examination method described in IWA-2213.

Licensees shall perform the ISI and testing of snubbers in accordance with ASME Section XI or the OM Code and the applicable addenda as required by 10 CFR 50.55a(g) or 10 CFR 50.55a(b)(3)(v), except where the NRC has granted specific written relief, pursuant to 10 CFR 50.55a(g)(6)(i), or authorized alternatives pursuant to 10 CFR 50.55a(3). The regulation at 10 CFR 50.55a(a)(3) states that licensees may use alternatives to the requirements of 10 CFR 50.55a(g) when authorized by the NRC if (1) the proposed alternatives would provide an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Licensees have the option to control the ASME Code-required examination and testing of snubbers through their plants TS or other licensee-controlled documents (i.e., TRM etc.).

However, when these documents represent an alternative to the code requirements incorporated by reference in 10 CFR 50.55a, they must be authorized by the NRC, pursuant to 10 CFR 50.55a(a)(3), on a case by case basis. As stated in 10 CFR 50.55a(a)(3), the use of an alternative in lieu of the Code requirements is subject to Commission approval. Additionally, plant TS may require updating in accordance with 10 CFR 50.55a(g)(5)(ii) if needed to conform them to the program that is in effect for the 120-month ISI interval.

SUMMARY

OF ISSUE The staff has identified several instances in which nuclear power plant licensees have used a TRM, or other licensee-controlled documents and procedures which do not meet requirements of the Code of Record for the ISI and testing of snubbers without requesting approval to use these alternatives from the Commission. The staff is issuing this RIS to remind licensees that they must submit a request and receive NRC approval to use an alternative to control the examination and testing of snubbers through their plants licensee-controlled documents (i.e.,

TRM etc.), when they represent a departure from and are used in lieu of the ASME Section XI or OM Code requirements.

The regulation at 10 CFR 50.55a requires ISI of components (including supports) in accordance with ASME Section XI or OM Code requirements. The use of a TRM, or any other licensee-controlled documents that represent a departure from the Code requirements for snubber ISI and testing requires NRC approval. The use of alternatives in lieu of the Code requirements is addressed in 10 CFR 50.55a(a)(3). When requesting authorization to use an alternative, licensees must demonstrate the proposed alternative would provide an acceptable level of quality and safety, or they must demonstrate why compliance with the Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

RIS 2009-XX Page 4 of 5 In addition, for licensees using plant TS to control snubber examination and testing, the requirement to perform 10-year program updates in accordance with 10 CFR 50.55a(g)(4) still exists. If the TS represent an alternative to the requirements of the code edition and addenda specified in 10 CFR 50.55a(b) that is to be used for the ISI interval, licensees are required to request authorization from the NRC to use the alternative in accordance with 10 CFR 50.55a(a)(3). The regulation at 10 CFR 50.55a(g)(5)(ii) also requires that a licensee apply for an amendment to conform the TS to the revised program in cases where there is a conflict between the revised program and the TS.

Some licensees mistakenly concluded that the ISI and testing of snubbers is not a 10 CFR 50.55a regulatory requirement, because 10 CFR 50.55a requires ISI of components (including supports) without specifically mentioning snubbers and since snubber examination and testing was historically covered by a plants TS. The resulting confusion led some licensees to believe that they do not need to request NRC approval to use an alternative (i.e., TS, TRM, or other licensee-controlled documents) in lieu of the Code requirements. The Commission has clarified, however, that snubber inspection and testing is a regulatory requirement.

Typically, if licensees use TS, TRM, or any other licensee-controlled documents which represent a departure from the ASME Code requirements for the ISI and testing of snubbers, they would submit an alternative for NRC approval as required by 10 CFR 50.55a(a)(3). The authorized alternative becomes a regulatory requirement that may be used in lieu of ASME Section XI or OM Code requirements for performing the ISI and testing of snubbers. The NRC staff must review and approve changes to these requirements for authorization under 10 CFR 50.55a(a)(3) or as an exemption under 10 CFR 50.12, Specific Exemptions. Alternatives requested and authorized pursuant to 10 CFR 50.55a(a)(3) are only valid for that particular 10-year ISI interval, unless specifically authorized for a different period in the associated NRC safety evaluation. In a subsequent 10-year ISI interval, licensees must resubmit an alternative for NRC staff review and approval if they choose not to adopt the ASME Code edition and addenda specified in the regulations for snubber examination and testing. In addition, for program changes that create a conflict with the plant TS, the licensee shall apply for an amendment to conform the TS to the program in accordance with 10 CFR 50.55a(g)(5)(ii).

BACKFIT DISCUSSION This RIS reminds stakeholders of existing regulatory requirements within 10 CFR 50.55a(b) and 10 CFR 50.55a(g) for the ISI and testing of dynamic restraints (snubbers). This RIS does not represent a new or different staff position about the implementation of 10 CFR 50.55a. This RIS reminds addressees of the need to request NRC approval for the use of TS, TRM, or other licensee-controlled documents in lieu of the ASME Code requirements as required by 10 CFR 50.55a(a)(3). It requires no action or written response beyond what is required in 10 CFR 50.55a. Any action that addressees take to implement procedural or inspection changes in accordance with the information in this RIS ensures compliance with current regulations; and therefore, is not a backfit under 10 CFR 50.109, Backfitting and specifically the exception provided for in 10 CFR 50.109(a)(4)(i). Consequently, the NRC staff did not perform a backfit analysis.

RIS 2009-XX Page 5 of 5 FEDERAL REGISTER NOTIFICATION A notice of opportunity for public comment on this RIS was published in the Federal Register on XXXX XX, 2009. There were XX comments from stakeholders, which were considered before issuance of this RIS (Agencywide Documents Access and Management System Accession No. MLXXXX.

CONGRESSIONAL REVIEW ACT The NRC has determined that this RIS is not a rule under 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 new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing collection requirements under 10 CFR Part 50 were approved by the Office of Management and Budget, control number 3150-0011.

PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, an information collection 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 to 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:

Gurjendra S. Bedi, NRR/DCI/CPTB 301-415-1393 E-mail: Gurjendra.Bedi@nrc.gov

RIS 2009-XX Page 5 of 5 FEDERAL REGISTER NOTIFICATION A notice of opportunity for public comment on this RIS was published in the Federal Register on XXXX XX, 2009. There were XX comments from stakeholders, which were considered before issuance of this RIS (Agencywide Documents Access and Management System Accession No. MLXXXX).

CONGRESSIONAL REVIEW ACT The NRC has determined that this RIS is not a rule under 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 new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing collection requirements under 10 CFR Part 50 were approved by the Office of Management and Budget, control number 3150-0011.

PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, an information collection 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 to 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:

Gurjendra S. Bedi, NRR/DCI/CPTB 301-415-1393 E-mail: Gurjendra.Bedi@nrc.gov DISTRIBUTION: DCI R/F ADAMS ACCESSION NO.: ML091660539 OFFICE NRR/DCI/CPTB Tech Editor NRR/DCI/CPTB OGC(CRA)

D: NRR/DCI NAME GSBedi KAzariah-Kribbs JMcHale SCroston MEvans DATE 05/29/2009 06/03/2009 07/14/2009 06/19 /2009 07/17/2009 OFFICE OE NRR/PMDA OIS OGC(NLO)

NAME NHilton LHill JHolonich EWilliamson DATE 08/18/2009 08/17/2009 08/20/2009 08/31/2009 OFFICE LA: PGCB PM: PGCB BC: PGCB D:NRR/DPR NAME CHawes SStuchell MMurphy TMcGinty DATE 11/18/2009 09/ 01 /2009 09/ /2009 09/ /2009 OFFICIAL RECORD COPY