Information Notice No. 81-15: Degradation of Automatic ECCS Actuation Capability by Isolation of Instrument Lines
SSINS No.: 6835 Accession No.: 8011040286 IN 81-15 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C, 20555 April 22, 1981 Information Notice No. 81-15: DEGRADATION OF AUTOMATIC ECCS ACTUATION CAPABILITY BY ISOLATION OF INSTRUMENT LINES Description of Circumstances: On March 23, 1981 at Georgia Power Company's Hatch Unit 2, an instrument technician, while investigating a drywell low-pressure alarm, found that seven of eight isolation valves were closed. The eighth valve was found slightly open and was considered as being functionally closed. These safety-related valves (also identified as panel or root valves) isolated twelve instruments that automatically actuate emergency core cooling systems (ECCS), reactor protection system, and containment isolation systems on high drywell pressure. The capability for manual actuation of the affected systems was continuously available from the control room. However, had a loss-of-coolant accident occurred, all systems would have been actuated by a redundant signal of low reactor water level, except for the automatic depressurization system. Those valves discovered to be closed were opened, valve alignment checks were performed, and no other discrepancies were found. These isolation valves were incorrectly identified as instrument drain valves and were closed on March 9, 1981 during completion of a valve lineup procedure. The drain valves that were being closed were on other safety-related lines that were of the same size and appearance as the high drywell pressure instrument lines that were isolated. Another event involving closure of some similar isolation valves was recently reported by the Peach Bottom Unit 2 licensee on April 1, 1981. The closed valves were found by a licensee employee who was troubleshooting an intermittent drywell pressure switch trouble alarm. Only one isolation valve was found fully closed, whereas two other valves were found one-eighth turn open (but considered closed for review of protective system responses). Redundant channels were verified to be operable; thus, no automatic protective or emergency cooling system actuation would have been lost from the high drywell pressure signal. This information is provided as an early notification of a possibly significant matter that is still under review by the NRC staff. In case the continuing NRC review finds that specific licensee actions would be appropriate, an IE bulletin or circular may be issued. In the interim, we expect that licensees will review this information for applicability to their operating procedures, paying particular attention to valve alignment checklists and requirements for independent verification of valve alignments including instrument valves. . IN 81-15 April 22, 1981 Page 2 of 2 No written response to this information notice is required. If you need additional information with regard to this matter, contact the Director of the appropriate NRC Regional Office. Attachment: Recently issued IE Information Notices
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021