NRC use of the terms, "Important to Safety" and "Safety Related" (Generic Letter No. 84-01)
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555
JANUARY 5, 1984
TO ALL HOLDERS OF OPERATING LICENSES, APPLICANTS FOR OPERATING LICENSES AND
HOLDERS OF CONSTRUCTION PERMITS FOR POWER REACTORS
Gentlemen:
Subject: NRC use of the terms, "Important to Safety" and "Safety Related"
(Generic letter 84-01)
As you may know, there has been concern expressed recently by the utility
classification group over NRC use of the terms "important to safety" and
"safety-related." The concern appears to be principally derived from recent
licensing cases in which the meaning of the terms in regard to NRC quality
assurance requirements has been at issue, and from a memorandum from the
Director, Office of Nuclear Reactor Regulation, to NRR personnel dated
November 20, 1981.
Enclosed for your information are two letters to the NRC from this group,
and the NRC response dated December 19, 1983. In particular, you should note
that the NRC reply makes it very clear that NRC regulatory jurisdiction
involving a safety matter is not controlled by the use of terms such as
"safety-related" and "important to safety," and our conclusion that pur-
suant to our regulations, nuclear power plant permittees or licensees are
responsible for developing and implementing quality assurance programs for
plant design and construction or for plant operation which meet the more
general requirements of General Design Criterion for plant equipment
"important to safety," and the more prescriptive requirements of Appendix B
to 10 CFR part 50 for "safety-related" plant equipment.
While previous staff licensing reviews were not specifically directed
towards determining whether, in fact permittees, or licensees have developed
quality assurance programs which adequately address all structures, systems
and components important to safety, this was not because of any concern over
the lack of regulatory requirements for this class of equipment. Rather, our
practice was based upon the staff view that normal industry practice is
generally acceptable for most equipment not covered by Appendix B within
this class. Nevertheless, in specific situations in the past where we have
found that quality assurance requirements beyond normal industry practice
were needed for equipment "important to safety," we have not hesitated in
imposing additional requirements commensurate with the importance to safety
of the equipment involved. We intend to continue that practice.
8401050382
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The NRC staff is interested in your comments and views on whether further
guidance is needed related to this issue. If you are interested in
participating in a meeting with NRC to discuss this subject please contact
Mr. James M. Taylor, Deputy Director, Office of Inspection and Enforcement.
Sincerely,
Darrell G. Eisenhut, Director
Division of Licensing
Enclosure:
1. Two Letters from Utility Safety Classification Group
2. NRC Response dated December 19, 1983
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