Information Notice No. 82-11:Potential Inaccuracies in Wide Range Pressure Instruments Used in Westinghouse Designed Plants
SSINS No.: 6835
IN 82-11
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
April 9, 1982
Information Notice No. 82-11: POTENTIAL INACCURACIES IN WIDE RANGE
PRESSURE INSTRUMENTS USED IN WESTINGHOUSE
DESIGNED PLANTS
Addressees:
All nuclear power reactor facilities holding an operating license or a
construction permit. (This information was transmitted by facsimile on
April 9, 1982 to Westinghouse designed nuclear power plants holding an
operating license.)
Purpose:
This Information Notice is provided as an early notification of a
potentially significant problem pertaining to wide range pressure
instruments used in Westinghouse nuclear power plans. It is expected that
recipients will review the information for applicability to their
facilities. No specific action or response is required at this time.
Description of Circumstances:
By telephone calls on April 7 and 8, 1982, Westinghouse notified the NRC of
information it had conveyed to its customers regarding the results of recent
qualification tests in post-accident high energy line break environment on
the wide range pressure instruments supplied by Westinghouse. Westinghouse
stated that when combining transmitter, signal conditioning and indicator
allowances for errors due to calibration uncertainty, drift and
environmental effects that the qualification tests indicated that the RCS
wide range pressure channels exhibited ambiguities in their accuracy which
could potentially result in inappropriate operator actions.
Westinghouse stated that post-accident accuracy ambiguities for RCS wide
range pressure instruments under certain plant accident conditions have the
potential for maximum accumulated inaccuracies of +/- 363 psig actuation and
+/- 390 psig indication. Accordingly, the inaccuracy of RCS wide range
pressure measurements could lead to pressurizer power operated relief valves
being lifted prior to the termination of safety injection (SI) and to a
greater number of valve challenges, thereby increasing the probability of a
small break loss-of-coolant accident due to a valve failing to close.
Likewise, the inaccuracy of the wide range pressure instruments could lead
to the termination of SI without adequate reactor coolant subcooling. In
addition, the inaccuracies could lead to premature or late tripping of the
RCS pumps during the course of a small break loss-of-coolant accident.
.
IN 82-11
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Westinghouse further stated that it is reviewing the design and operational
bases for the wide range pressure instrumentation, that it will advise its
customers of appropriate actions, and that continued safe plant operation
has been demonstrated by prior analyses.
If you have any questions regarding this matter, please contact the Regional
Administrator of the appropriate NRC Regional Office, or this office.
Edward L. Jordan, Director
Division of Engineering and
Quality Assurance
Office of Inspection and Enforcement
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