HomeMy WebLinkAbout851177.tiff SS INS No. : 6835 mitt
IN 85-17, Supplement 1
UNITED STATES 1NELD COUM}9
NUCLEAR REGULATORY COMMISSION p
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555
OCT l6 as
October 1, 1985 _ it
it4-4.4.I.EY. COLA_
IE INFORMATION NOTICE NO. 85-17, SUPPLEMENT 1: SOLENOID VAL
VES
STICKING CI OF ASCO
Addressees:
All nuclear power reactor facilities holding an operating license (OL) or a
construction permit (CP).
Purpose:
This notice is to inform recipients of the results of followup investigations
regarding the reasons for sticking of Automatic Switch Company (ASCO) solenoid
valves used to shut main steam isolation valves (MSIVs) under accident conditions.
Recipients are expected to review the information for applicability to their
facilities and consider actions, if appropriate, to preclude similar problems
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:
Information Notice No. 85-17, "Possible Sticking of ASCO Solenoid Valves,"
described the problem that occurred with ASCO Model HTX 832320V solenoid valves
at Grand Gulf Unit 1.
General Electric (GE) and ASCO conducted tests to determine the cause and any
further corrective actions. The following is a summary of the GE and ASCO
tests and analyses:
Two of the three solenoid valves which failed at the Grand Gulf Nuclear
Station also sporadically failed to transfer during testing at elevated
temperatures. These two valves were the only valves that failed during
these tests. However, these failures were not predictable. Subsequently,
five valves from Grand Gulf service were disassembled and inspected. This
inspection identified a microscopic foreign substance on the lower
core/plug nut interfaces on all five valves.
Further evaluations of this microscopic substance were inconclusive because
of the small foreign substance sample size. After cleaning and reassembly
of these valves, tests were conducted on four of these five valves at
elevated temperatures. These four valves functioned normally. ASCO felt
certain that the valve failures resulted from high-temperature sticking of
the lower core-to-plug nut faces resulting from a foreign substance or
combination of substances collected at this interface.
851177
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IN 85-17, Supplement 1
October 1, 1985
Page 2 of 2
A detailed dimensional analysis and comparison among the valves returned
from Grand Gulf indicated that all parts were within allowable limits and
differences were not enough to cause a failure to shift. Therefore, this
examination tended to relieve concerns related to a generic design defect.
GE has attempted to locate additional foreign substance from other valves
of the same type in use at Grand Gulf to determine how the foreign substance
got in the valve, or where it originated. GE was able to scrape some small
amounts of foreign substance from the lower core-to-plug nut interface.
However, there was not enough residue to make a definitive identification
of the nature of the foreign substance.
GE has recommended that the licensee replace the potentially contaminated MSIV
solenoid valves and institute a periodic examination and cleaning of the MSIV
solenoid valves. Grand Gulf has replaced the eight MSIV HTX832320V dual
solenoid valves with fully environmentally qualified ASCO Model NP 8323A20E
dual solenoid valves. The environmentally qualified valve Model NP 8323A20E
was included in a control sample placed in the test ovens with the solenoid
valves that stuck at Grand Gulf. The environmentally qualified model did not
stick under the test conditions that cause sticking in the other solenoid
valves.
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.
Jar/ Srector
Divisi of Emergency Preparedness
and gineering Response
Office of Inspection and Enforcement
Technical Contact: Eric Weiss, IE
(301) 492-9005
Attachment: List of Recently Issued IE Information Notices
Attachment 1
IN 85-17, Supplement 1
October 1, 1985
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
85-79 Inadequate Communications 9/30/85 All power reactor
Between Maintenance, facilities holding
Operations, And Security an OL or CP; research
Personnel and nonpower reactor
facilities; fuel
fabrication and
processing facilities
85-78 Event Notification 9/23/85 All power reactor
facilities holding
an OL or CP
85-77 Possible Loss Of Emergency 9/20/85 All power reactor
Notification System Due To facilities holding
Loss Of AC Power an OL or CP
85-76 Recent Water Hammer Events 9/19/85 All power reactor
facilities holding
an OL or CP
85-75 Improperly Installed Instru- 8/30/85 All power reactor
mentation, Inadequate Quality facilities holding
Control And Inadequate Post- an OL or CP
modification Testing
85-74 Station Battery Problems 8/29/85 All power reactor
facilities holding
an OL or CP
84-70 Reliance On Water Level 8/26/85 All power reactor
Sup. 1 Instrumentation With A facilities holding
Common Reference Leg an OL or CP
85-73 Emergency Diesel Generator 8/23/85 All power reactor
Control Circuit Logic Design facilities holding
Error an OL or CP
85-72 Uncontrolled Leakage Of 8/22/85 All power reactor
Reactor Coolant Outside facilities holding
Containment an OL or CP
OL = Operating License
CP = Construction Permit
SSINS No. : 6835
IN 85-79
UNITED STATES Q w��
NUCLEAR REGULATORY COMMISSION L
OFFICE OF INSPECTION AND ENFORCEMENT OCT 8 WASHINGTON, D.C. 20555
sas
September 30, 1985 � tLt
IE INFORMATION NOTICE NO. 85-79: INADEQUATE COMMUNICATIONS BETWEEN MAINTENANCE,
OPERATIONS, AND SECURITY PERSONNEL
Addressees:
All nuclear power reactor facilities holding an operating license (OL) or
construction permit (CP), research and nonpower reactor facilities, and fuel
fabrication and processing facilities using or processing formula quantities
of special nuclear material .
Purpose:
This information notice is provided to alert addressees of the need to ensure
that actions of a temporary or permanent nature taken by operations, maintenance,
or other personnel that may affect the integrity of the physical barriers used
to control access to protected, material access, and vital areas, or other por-
tions of the overall security program, are coordinated with the organization '
directly responsible for security before being implemented. It is expected
that the recipients will review the information for applicability to their
facilities and consider actions , if necessary, to preclude a similar problem
occurring at their facilities. Suggestions contained in this information
notice do not constitute NRC requirements; therefore, no specific action or
written response is required.
Description of Circumstances:
During plant walkdowns and/or inspections, NRC and licensee personnel have
identified instances where actions by plant organizational elements other than
security have resulted in the degradation of protected and vital area barriers
and other security/safeguards measures without proper compensation. Some
examples are:
o removal of portions of protected and vital area barriers, including
fences, hatches, or other portals that allow unauthorized access to
the protected area or vital areas
o removal of equipment that had formed part of the barrier, such as
piping or valves that would allow passage of small objects into or
out of a material access area or vital area
o creation of holes in protected and vital area barriers to facilitate
construction
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IN 85-79
September 30, 1985
Page 2 of 3
o leaving vital area door alarms in access mode after work is completed
o removal of essential telephone lines from an independent power source
o building or placing equipment, structures, or vehicles within the
isolation zone of the protected area or within exterior "clear" zones
of sensitive facilities, such as storage vaults
The incidents that lead to the issuance of this information notice have resulted
in the degradation of protected and vital area barriers and access controls
necessary for protection of vital equipment and, in one case, the loss of the
means to communicate with local law enforcement officials or emergency response
personnel . In many cases, the loss of this protection has been accompanied by
the failure of the licensee to notify the NRC in accordance with the applicable
provisions of 10 CFR 73. 71, depending on the degree to which the security system
has been degraded.
Discussion:
A review of each incident has indicated that the modification or repairs that
degraded the protected and vital area barriers and communications systems were
made without an adequate, or in some cases any, notification of the facility' s
security organization by the organization planning or performing the modifica-
tions or repairs.
The likelihood of degradation may be substantially lessened at sites where the
organization responsible for security is part of the planning or scheduling
phase of any facility modifications or repairs. In such facilities, the
barriers and equipment necessary to provide security to the facility are
identified and the proper compensatory measures planned and scheduled to allow
for the efficient implementation of the planned modifications or repairs. An
integrated planning system allows for all facility organizations to have input
to the planning and scheduling phase of maintenance and facility modifications,
especially when the actions taken can negatively impact on the effectiveness of
other essential programs.
The reporting requirements of 10 CFR 73. 71 may apply to security incidents of
the type described above, depending on the degree to which the security system
has been degraded.
IN 85-79
September 30, 1985
Page 3 of 3
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 approprate NRC regional office or this office.
dward . io d, Director
Divisi n •f Emergency Preparedness
and gineering Response
Office of Inspection and Enforcement
Technical Contact: R. Rosano, IE
(301) 492-4006
Attachment: List of Recently Issued IE Information Notices
Attachment 1
IN 85-79
September 30, 1985
LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
85-78 Event Notification 9/23/85 All power reactor
facilities holding
an OL or CP
85-77 Possible Loss Of Emergency 9/20/85 All power reactor
Notification System Due To facilities holding
Loss Of AC Power an OL or CP
85-76 Recent Water Hammer Events 9/19/85 All power reactor
facilities holding
an OL or CP
85-75 Improperly Installed Instru- 8/30/85 All power reactor
mentation, Inadequate Quality facilities holding
Control And Inadequate Post- an OL or CP
modification Testing
85-74 Station Battery Problems 8/29/85 All power reactor
facilities holding
an OL or CP
84-70 Reliance On Water Level 8/26/85 All power reactor
Sup. 1 Instrumentation With A facilities holding
Common Reference Leg an OL or CP
85-73 Emergency Diesel Generator 8/23/85 All power reactor
Control Circuit Logic Design facilities holding
Error an OL or CP
85-72 Uncontrolled Leakage Of 8/22/85 All power reactor
Reactor Coolant Outside facilities holding
Containment an OL or CP
85-71 Containment Integrated Leak 8/22/85 All power reactor
Rate Tests facilities holding
an OL or CP
85-70 Teletherapy Unit Full 8/15/85 All material
Calibration And Qualified licensees
Expert Requirements (10 CFR
35. 23 And 10 CFR 35. 24)
OL = Operating License
CP = Construction Permit
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