Bulletin 78-14: Deterioration of Buna-N Components in ASCO Solenoids
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
December 19, 1978
IE Bulletin No. 78-14
DETERIORATION OF BUNA-N COMPONENTS IN ASCO SOLENOIDS
Description of Circumstances:
Following a reactor scram at the Monticello Nuclear Power Station on July
27, 1973, one control rod was determined to have a slow scram insertion
time. While measuring the average control rod scram insertion times (as
required by Technical Specifications), the same control rod failed to scram.
Subsequent investigation revealed that a Buna-N disc in the scram pilot
valve solenoid core assembly had fractured. Small pieces of the Buna-N
material wedged between the core assembly and the valve pilot body. This
prevented proper movement of the core assembly (plunger), and thus prevented
the valve from properly venting control air from the scram valves. A similar
event occurred during scram testing on June 5, 1978. On both occasions the
control rod failed to scram during control rod surveillance testing. In
these instances, had a scram occurred during normal operation of the
reactor, the affected rods would have inserted by action of the backup scram
solenoid valves.
The reactor was placed in cold shutdown on July 28, 1978. All of the scram
pilot solenoid valves and scram backup valves were disassembled and
inspected. Six additional fractured Buna-N discs were found, all in scram
pilot solenoid valves. Northern States Power Company replaced the plunger
Buna-N discs in all 242 scram pilot valves and the 2 backup scram valves.
In addition to the Monticello failures, similar events were recently
reported from the Big Rock Point and Pilgrim facilities. At Big Rock Point,
two failures were experienced in October while at Pilgrim one failure was
found in July and two in December. All of these failures were encountered
during surveillance testing.
General Electric had previously issued Service Information Letters, SIL 128
(March 31, 1975) and SIL 123 Revision 1 (January 30, 1976), addressing the
deterioration through natural aging of Buna-N components in CRD scram pilot
valves. These letters recommended that a maintenance program be adopted
which replaced certain Buna-N components in scram pilot valves on a
regularly scheduled basis. However, the Buna-N discs
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IE Bulletin No. 78-14 December 19, 1978
in the scram pilot valve core assemblies were not included in these
recommendations. As a result of the Monticello experience and subsequent
investigation, General Electric has issued in August 1978, SIL 128 Revision
1, Supplement 1, which recommends that all BWR operators take the following
actions:
"Establish a preventive maintenance program to replace all core
assemblies, diaphragms and associated parts in all CRD scram pilot
valves, backup scram valves, scram discharge volume vent and drain
pilot valves, and scram discharge volume test valves, at periodic
intervals. The Buna-N parts used in these valves have at least a seven
year shelf and in-service life from the packaging date on the rebuild
kit. Thus, the valves should be rebuilt periodically to assure that the
Buna-N parts are not used in excess of seven years. It is recommended
that the work be scheduled in any one outage such that the associated
CRDs are selected from a distributed checkerboard pattern. The
remaining valves can be rebuilt during subsequent outages."
For clarity, it is noted that the above seven year limit recommended by GE
includes all of the time from packaging through installation to the end of
service life. In addition, it is noted that the March 31, 1975 issue of SIL
128 stated that the design specification for Buna-N specified a minimum
design life of three years.
Action to be Taken by Licensees:
For all GE BWR power reactor facilities with an operating license:
1. Review Buna-N material applications in your control rod scram systems
and determine the time since installation, and for installed material,
the time since packaging.
2. Report the results of the review set forth in item 1 above and describe
your schedule for replacement, both in response to this Bulletin and
for periodic maintenance.
3. Describe the bases for your schedule of replacement identified in
response to item 2 above. Justify any proposed replacement time in
excess of three years.
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IE Bulletin No. 78-14 December 19, 1978
4. Within 45 calendar days of the date of issue of this Bulletin, report
in writing to the Director of the appropriate NRC Regional Office, the
results of your review, schedule and bases for replacement with regard
to Items 1 through 3. A copy of your report should be sent to the
United States Nuclear Regulatory Commission, Office of Inspection and
Enforcement, Division of Reactor Operations Inspection, Washington,
D.C. 20555.
For all BWR facilities with a construction permit and all other power
reactor facilities with an operating license or construction permit, this
Bulletin is for information only and no written response is required.
Approved by GAO B180225 (R0072); clearance expires 7/31/80. Approval was
given under a blanket clearance specifically for identified generic
problems.
Enclosure:
List of IE Bulletins
Issued in 1978
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