96-24695. Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves; Issued

[Federal Register Volume 61, Number 188 (Thursday, September 26, 1996)]
[Notices]
[Page 50514]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-24695]


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NUCLEAR REGULATORY COMMISSION

Periodic Verification of Design-Basis Capability of Safety-
Related Motor-Operated Valves; Issued

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of issuance.

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SUMMARY: The Nuclear Regulatory Commission (NRC) has issued Generic 
Letter 96-05 to all holders of operating licenses (except those 
licenses that have been amended to possession-only status) or 
construction permits for nuclear power reactors, to (1) discuss the 
periodic verification of the capability of safety-related motor-
operated valves to perform their safety functions consistent with the 
current licensing basis of nuclear power plants, (2) request that each 
addressee of this generic letter establish a program, or ensure the 
effectiveness of its current program, to verify on a periodic basis 
that safety-related MOVs continue to be capable of performing their 
safety functions within the current licensing basis of the facility, 
and (3) require addressees to provide to the NRC a written response 
relating to implementation of the requested action. This generic letter 
is available in the NRC Public Document Room under accession number 
9609100488.

DATES: The generic letter was issued on September 18, 1996.

ADDRESSEES: Not applicable.

FOR FURTHER INFORMATION CONTACT: Thomas G. Scarbrough, at (301) 415-
2794.

SUPPLEMENTARY INFORMATION: NRC regulations require that components that 
are important to the safe operation of a nuclear power plant, including 
motor-operated valves (MOVs), be treated in a manner that provides 
assurance of their performance. Appendix A, ``General Design Criteria 
for Nuclear Power Plants,'' and Appendix B, ``Quality Assurance 
Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,'' to 
Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50) 
include broad-based requirements in this regard. In 10 CFR 50.55a(f), 
the NRC requires licensees to comply with Section XI of the American 
Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME 
Code).
    Nuclear power plant operating experience, valve performance 
problems and MOV research have revealed that the focus of the ASME Code 
on stroke time and leak-rate testing for MOVs was not sufficient for 
ensuring the long-term capability of MOVs to perform their design-basis 
safety functions in light of the design of the valves and the 
conditions under which they must function. For this reason, on June 28, 
1989, the NRC staff issued Generic Letter (GL) 89-10, ``Safety-Related 
Motor-Operated Valve Testing and Surveillance.'' In GL 89-10, the staff 
requested that certain actions be taken to ensure the capability of 
MOVs in safety-related systems to perform their intended functions. The 
staff issued seven supplements to GL 89-10 that provided additional 
guidance and information.
    GL 89-10 and its supplements provide only limited guidance 
regarding periodic verification and the measures appropriate to assure 
preservation of design-basis capability. This generic letter provides 
more complete guidance regarding periodic verification of safety-
related MOVs and supersedes GL 89-10 and its supplements with regard to 
MOV periodic verification. Although this guidance could have been 
provided in a supplement to GL 89-10, the staff has prepared this new 
generic letter to allow closure of the staff review of GL 89-10 
programs as promptly as possible.

    Dated at Rockville, Maryland, this 18th day of September 1996.

    For the Nuclear Regulatory Commission.
Thomas T. Martin,
Director, Division of Reactor Program Management Office of Nuclear 
Reactor Regulation.
[FR Doc. 96-24695 Filed 9-25-96; 8:45 am]
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