Potential Unreviewed Safety Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems (Generic Letter 79-42)
GL79042
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON. D. C, 20555
September 17, 1979
ALL OPERATING LIGHT WATER REACTORS
SUBJECT: POTENTIAL UNREVIEWED SAFETY QUESTION ON INTERACTION BETWEEN
NON-SAFETY GRADE SYSTEMS AND SAFETY GRADE SYSTEMS
You were informed by IE Information Notice 79-22, issued September 14, 1979,
that certain non-safety grade equipment, if subjected to an adverse
environment, could impact the safety analyses and the adequacy of the
protective functions performed by safety grade equipment. Enclosed is a copy
of IE Information Notice 79-22, and reprinted copies of an August 30, 1979
Westinghouse letter and a September 10, 1979 Public Service Electric and Gas
Company letter which address this matter.
The NRC is concerned that a similar potential may exist at other operating
light water reactor facilities, including yours, for an unreviewed safety
matter related to the effects of the environment on control systems
resulting from high energy line breaks inside or outside containment and the
results of these effects on the required safety systems.
In accordance with 10 CFR 50.54(f) you are requested to provide within
twenty (20) days of the date of this letter, written statements, signed
under oath or affirmation, which will enable the staff to determine, in
light of the concerns discussed above, whether or not your NRC license(s) to
operate your nuclear power generating facility(ies) should be modified,
suspended, or revoked.
Sincerely,
Harold R. Denton, Director
Office of Nuclear Reactor Regulatory
Enclosures:
1. IE Information Notice 79-22
2. Westingthouse's August 30, 1979 Letter
(Reprint)
3. Public Service Electric and Gas
Company's September 10, 1979 Letter
(Reprint)
Page Last Reviewed/Updated Tuesday, March 09, 2021