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.
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