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NRC RIN: 3150-AE26 Publication ID: Spring 1997 
Title: Codes and Standards for Nuclear Power Plants 
Abstract: The proposed rule would amend the Commission's regulations to (1) eliminate the 120-month update requirements for licensees' inservice inspection (ISI) and inservice testing (IST) programs; (2) establish baseline regulatory requirements that would: incorporate by reference the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (the OM Code), maintain the 1989 Edition of section III and section XI of the ASME Boiler and Pressure Vessel Code (the BPV Code), require certain licensees to complete one final update to their ISI and IST programs, and delete the existing supplementary requirements for IST of containment isolation valves; (3) allow alternatives to the regulations and ASME Code rules under certain circumstances such as the temporary corrective measures identified in a new appendix A to the regulations, and clarify the ISI and IST requirements for nuclear plant components not required to be constructed in accordance with ASME Code Class 1, 2, or 3; (4) identify safety-significant Code changes that would be required to be implemented by licensees; and (5) establish a new regulatory guide that would document NRC review and acceptance of OM Code Cases. ^PEliminating the 120-month update requirements from the existing regulations would permit licensees to continue using their existing ISI and IST programs; however, certain licensees that have not yet updated the 1989 Edition of section XI of the ASME BPV Code would be required to implement one final update of their ISI and IST programs when their current intervals expire. The proposed rule would incorporate by reference the ASME OM Code into the regulations. ^PThe proposed rule would allow alternatives to the regulations and ASME Code rules under certain circumstances. For example, the NRC staff has developed an alternative to the requirements of section XI of the ASME BPV Code that specifies guidance for performing temporary corrective measures for service-induced degradation of ASME Code Class 3 piping, which has been added as an appendix to the rule. Other alternatives that the staff has found acceptable will be identified in the rule or in a regulatory guide. 
Agency: Nuclear Regulatory Commission(NRC)  Priority: Substantive, Nonsignificant 
RIN Status: Previously published in the Unified Agenda Agenda Stage of Rulemaking: Long-Term Actions 
Major: No  Unfunded Mandates: No 
CFR Citation: 10 CFR 050   
Legal Authority: 42 USC 2201    42 USC 5841   
Timetable:
Action Date FR Cite
NPRM  To Be Determined    
Additional Information: If a licensee elects to implement the alternatives listed in the regulatory guide, a request pursuant to 10 CFR 50.55a(a)(3) must be submitted. All safety-significant code changes that the staff determines to be cost beneficial for the safe operation of the nuclear power plants will be specifically imposed in the regulations. One example in the current rulemaking is the requirement that licensees implement section XI, appendix VIII, "Performance Demonstration for Ultrasonic Examination System," which provides rules for performance demonstration for ultrasonic examination procedures, equipment, and personnel used to detect and size flaws in nuclear power plant components, which will be imposed on an expedited schedule to improve the quality of ISI. ^PThe proposed amendment contains changes to the implementation structure of 10 CFR 50.55a, establishes alternative rules (to be contained in the rule or listed in a regulatory guide) which may be implemented by licensees on a voluntary basis (and may require prior NRC approval), and identifies safety-significant code changes that should be implemented by licensees. These actions support substantial reductions in regulatory burden, without an adverse impact on safety, as determined by the staff during the review of a cost-beneficial licensing action request.
Regulatory Flexibility Analysis Required: No  Government Levels Affected: None 
Included in the Regulatory Plan: No 
Agency Contact:
Frank Cherny
Nuclear Regulatory Commission
Office of Nuclear Regulatory Research,
Washington, DC 20555-0001
Phone:301 415-6786
Email: fcc1@nrc.gov

Wan Cheng Liu
Nuclear Regulatory Commission
Office of Nuclear Reactor Regulation,
Washington, DC 20555
Phone:301 415-3148
Email: wcl2@nrc.gov