Information Notice No. 86-82, Revision 1: Failures of Scram Discharge Volume Vent and Drain Valves
SSINS No.: 6835
IN 86-82, Revision 1
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
November 4, 1986
Information Notice No. 86-82, REVISION 1: FAILURES OF SCRAM DISCHARGE
VOLUME VENT AND DRAIN VALVES
Addressees:
All nuclear power reactor facilities holding an operating license or a
construction permit.
Purpose:
This notice is provided to inform recipients of a potentially significant
problem pertaining to failures of the Hammel-Dahl valves used as vent and
drain valves in the control rod drive (CRD) systems of certain boiling water
reactors. It is suggested that recipients will review the information for
applicability to their facilities and consider actions, if appropriate, to
preclude a similar problem from occurring at their facilities. However,
suggestions contained in this information notice do not constitute NRC
requirements; therefore, no specific action or written response is required.
Description of Circumstances:
On February 8, 1985, the General Electric Company (GE) notified the NRC of a
coupling failure of the 2"-2500# Hammel-Dahl valve used as a CRD drain valve
in the scram discharge volume (SDV). The coupling connected the air actuator
to the valve stem and its failure prevented the valve from fully opening or
closing. This failure had occurred during equipment qualification in a
laboratory and was due to automatic actuation while the manual handwheel was
partially engaged.
GE identified the 2"-600#, 1"-2500#, and 1"-600# as having the same coupling
design. The 1" valves are used as SDV vent valves.
On May 13, 1985, GE issued service information letter (SIL) 422 to inform
its customers of the potential for failure of the valve and recommended
actions. In SIL 422, GE mentions a related problem that occurred at an
operating plant.
Subsequently, two additional operating plants have experienced valve
failures caused by partially engaged handwheels: Limerick in November of
1985 and Hope Creek in May of 1986. Limerick found an SDV drain valve with
its handwheel off the neutral position and attempted to actuate the valve
from the control room. The valve would not operate. Hope Creek found a
coupling failed in a drain valve and the handwheel partially engaged. The
handwheel was in the neutral position as identified by the manufacturer's
installed nameplate, signifying that the nameplate was mislocated.
8610300071
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IN 86-82
November 4, 1986
Page 2 of 2
Discussion:
The SDV vent and drain valves are primary containment isolation valves that
are normally open while the plant is operating. There are two valves in
series in each vent and drain line. They allow water from the normal CRD
seal leakage to drain to radwaste rather than accumulate in the SDV. When a
scram occurs, the vent and drain valves close to isolate reactor coolant
from radwaste.
GE SIL 422 recommends that licensees "provide adequate training, operating
procedures, and checks to help assure that the handwheels of the valves are
in the neutral position to prevent inadvertent engagement of the handwheel
during automatic actuation of the valves."
When the handwheel is engaged or partially engaged, the automatic actuation
function may be prevented, or, if it occurs, may damage the actuator or stem
of the valve, causing it to fail in its "as-is" position. These valves are
primary containment isolation valves. If two valves in series fail open, a
discharge path will exist for reactor coolant to drain to the plant drain
system. This path can be isolated by resetting the scram signal or by
manually closing the #102 or #112 valves on each associated hydraulic
control unit (HCU). (There are approximately 92 HCUs per SDV.) If the vent
and drain valves fail closed, the CRD seal leakage will collect in the SDV
until the SDV level reaches the scram set point.
The failure of either redundant vent valve and or either redundant drain
valve represent a degradation of safety systems (CRD, primary containment,
and the primary containment isolation system) and could result in
unnecessary challenges of the reactor protection system. Licensee corrective
actions have included training, procedure revision, and enhanced
surveillance as well as adding administrative controls to maintain the
handwheels in the neutral position. Additionally, Hope Creek determined the
actual neutral position and relocated the nameplate.
No specific action or written response is required by this information
notice. If you have any questions about this matter, please contact the
Regional Administrator of the appropriate regional office or this office.
Edward L. Jordan Director
Division of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contact: Mary S. Wegner
(301) 492-4511
Attachment: List of Recently Issued IE Information Notices
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