Information Notice 2010-14, Containment Concrete Surface Condition Examination Frequency And Acceptance Criteria

Containment Concrete Surface Condition Examination Frequency And Acceptance Criteria

ML101600151
Person / Time
Issue date:	08/04/2010
Revision:	0
From:	McGinty T J, Tracy G M Office of Nuclear Reactor Regulation
To:
References
IN-10-014
Download: ML101600151 (5)

ML101600151 August 4, 2010 NRC INFORMATION NOTICE 2010-14: CONTAINMENT CONCRETE SURFACE CONDITION EXAMINATION FREQUENCY AND ACCEPTANCE CRITERIA

ADDRESSEES

All holders of an operating license or construction permit for a nuclear power reactor issued under 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 All holders of or applicants for standard design certification, standard design approval, or combined license issued under 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants."

PURPOSE

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice (IN) to inform addressees of recent issues identified by the NRC staff during license renewal application (LRA)

review audits at different nuclear power plant sites concerning the containment concrete surface condition examination frequency and acceptance criteri The NRC expects recipients to review the information for applicability to their facilities and consider actions, as appropriate, to avoid similar problem The suggestions that appear in this IN are not NRC requirements; therefore, no specific action or written response is require DESCRIPTION OF CIRCUMSTANCES During recent LRA audits, the NRC staff found that some nuclear plant licensees did not meet the requirements for containment concrete surface examinations specified in 10 CFR 50.55a,

"Codes and Standards," dated August 8, 1996, and in Article IWL-2510, "Surface Examination," of Subsection IWL, "Requirements for Class CC Concrete Components of Light-Water-Cooled Power Plants," of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Cod Specifically, 10 CFR 50.55a incorporates, by reference, Subsection IWL, which requires periodic inservice inspections (ISIs) of containment concret Paragraph IWL-2410(a), as modified by 10 CFR 50.55a(g)(6)(ii)(B)(2) based on the final rulemaking of August 8, 1996, states, "Concrete shall be examined in accordance with IWL-2510-[at all operating nuclear power plants by September 9, 2001] and every 5 years thereafter." However, during recent LRA audits of some multiple-unit nuclear power plants, the NRC staff found that some licensees IN 2010-14