Improper Installation of Patel Conduit Seals ML031210572 Person / Time Site:
Beaver Valley , Millstone , Hatch , Monticello , Calvert Cliffs , Dresden , Davis Besse , Peach Bottom , Browns Ferry , Salem , Oconee , Mcguire , Nine Mile Point , Palisades , Palo Verde , Perry , Indian Point , Fermi , Kewaunee , Catawba , Harris , Wolf Creek , Saint Lucie , Point Beach , Oyster Creek , Watts Bar , Hope Creek , Grand Gulf , Cooper , Sequoyah , Byron , Pilgrim , Arkansas Nuclear , Braidwood , Susquehanna , Summer , Prairie Island , Columbia , Seabrook , Brunswick , Surry , Limerick , North Anna , Turkey Point , River Bend , Vermont Yankee , Crystal River , Haddam Neck , Ginna , Diablo Canyon , Callaway , Vogtle , Waterford , Duane Arnold , Farley , Robinson , Clinton , South Texas , San Onofre , Cook , Comanche Peak , Yankee Rowe , Maine Yankee , Quad Cities , Humboldt Bay , La Crosse , Big Rock Point , Rancho Seco , Zion , Midland , Bellefonte , Fort Calhoun , FitzPatrick , McGuire , LaSalle , Fort Saint Vrain , Shoreham , Satsop , Trojan , Atlantic Nuclear Power Plant , Crane Issue date:
04/04/1990 From:
Rossi C Office of Nuclear Reactor Regulation To:
References IN-90-023 , NUDOCS 9003280088Download: ML031210572 (7)
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Beaver Valley ,
Millstone ,
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Calvert Cliffs ,
Dresden ,
Davis Besse ,
Peach Bottom ,
Browns Ferry ,
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Shoreham ,
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Atlantic Nuclear Power Plant ,
Crane Category:NRC Information Notice
[Table view] The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>.
UNITED STATES
Contents
1 NUCLEAR REGULATORY COMMISSION
2 April 4, 1990
3 IMPROPER INSTALLATION OF PATEL CONDUIT SEALS
4 Addressees
5 Purpose
6 Description of Circumstances
6.1 One union nut was found
6.2 Charles E. Rossi,lrector
6.3 Office of Nuclear Reactor Regulation
6.4 N. Merriweather, RII
6.5 Recent Events
6.6 O AND AMMD WMCWNOO0
6.7 April 4, 1990 January 2, 1990
6.8 Duquesne Light
6.9 Nebraska Public Power District
6.10 Omaha Public Power District
6.11 Wisconsin Public Service
6.12 Northern States Power
6.13 General Public Utilities
6.14 Beaver Valley
6.15 Calvert Cliffs
6.16 Oyster Creek
6.17 Productd irector
6.18 Attachment 1
6.19 April 4, 1990 MEMORANDUM
6.20 Elam, Products Director, EGS Corp
6.21 Recent Events Concerning Patel
6.22 November 7, 1989
6.23 Grommet Use Rangey
6.24 Attachment 1
6.25 April 4, 1990
6.26 Our experience with the Patel Conduit
6.27 This does not
6.28 As a precaution, at a convenient time, we
6.29 To verify torque, attempt
6.30 November 7, 1989
6.31 Attachment 1
6.32 April 4, 1990 Conclusion
6.33 All users should be aware of conduit seal use ranges
6.34 If there is reason to believe that use ranges and
6.35 We are in the process of revising the
6.36 The drawing will be
6.37 Attachment 2
6.38 April 4, 1990 LIST OF RECENTLY ISSUED
6.39 Unanticipated Equipment
6.40 Restoration of Power
6.41 Operated Butterfly Valves
6.42 Personnel Injuries Resulting
6.43 Radwaste Incinerators
6.44 Volume for Containment
6.45 PWR Facilities
6.46 Crosby Safety Relief Valves
6.47 Air Start Receiver Tanks
6.48 Gravity Discrepancies
6.49 Suppliers of Potentially
6.50 Compliance with New
6.51 All holders of OLs
6.52 All holders of OLs
6.53 All NRC licensees
6.54 All holders of OLs
6.55 All holders of OLs
6.56 All holders of OLs
6.57 All holders of OLs
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON , D.C.
20555
April 4, 1990
NRC INFORMATION NOTICE NO. 90-23:
IMPROPER INSTALLATION OF PATEL CONDUIT SEALS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
This information notice is intended to alert addressees to a possible safety
problem caused by the improper installation of Patel conduit seals as a result
of incorrect selection of grommets based on the wire gauge size.
It is ex- pected that recipients will review the information for applicability to their
facilities and consider actions, as appropriate, to avoid similar problems.
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 November 6, 1989, the staff at the H. B. Robinson plant notified the NRC that
they had discovered that some of the conduit seal grommets used to seal insu- lated wire conductors entering environmentally qualified instrument housings
were oversized for the application. The seals are used to prevent moisture
from entering safety-related electrical components following loss-of-coolant
accidents.
Use of oversized seals may create potential moisture intrusion
paths into safety-related instrumentation inside the reactor containment.
The problem was attributed to inadequate installation instructions that were
used when the seals were installed in 1986 and 1987. These instructions listed
the grommets by wire gauge size and gave maximum wire insulation diameters for
each wire size (see the first table, page 1, of the enclosed EGS Bulletin 90-1).
In accordance with these instructions, the seals were selected based on wire
gauge alone. However, since the insulation thickness for a given wire gauge
varies from one wire type to another, a more appropriate parameter for choosing
the correct grommet size would have been the minimum wire insulation diameter
for which a particular grommet will achieve an effective seal. The selection
of grommet size based only on wire gauge size resulted in the installation of
some grommets that were too large to provide an effective seal.
As a result, some of the seals failed pressure tests that were designed to simulate post- LOCA pressures.
Pd
Ia
0
N c*SC
.Volt
>E,
IN 90-23 April 4, 1990 During the investigation of the grommet leakage problem, the Robinson staff also
checked the torque on the conduit seal union nuts that are used to compress the
seals.
EGS Corporation recommends that the union nuts be torqued to 50 ft-lb
(EGS Bulletin 90-1).
On approximately half of the 90 seals inspected, the union
nut moved about 1/4 inch when this torque was applied.
One union nut was found
to be quite loose.
EGS Corporation reports that 1/4 inch of movement does not
necessarily indicate a degraded seal but recommends that the correct torque be
verified on a representative sample of installed conduit seals.
Discussion:
In order for these conduit seals to be able to function at accident pressures
and temperatures and for extended periods following an accident, it is impor- tant that the correct installation procedures be established and consistently
applied. In this case, the installation of the seals according to inadequate
procedures could have resulted in moisture intrusion into more than one safety
component during an accident, leading to equipment failures or the display of
erroneous information to the operators.
Although the vendor's use of wire range sizes to designate the grommets appears
to have been intended as an aid in choosing the proper grommet for the appli- cation, differences in insulation thicknesses because of differences in
insulating materials and type of application were not accounted for by either
the vendor's original instructions or the licensee's initial installation pro- cedures for the grommets . The necessary minimum insulation diameter values
for each grommet size were subsequently provided by EGS Corporation, the sup- plier of the Patel conduit seals. These minimum diameters are also included
in EGS Bulletin 90-1.
This information notice requires no specific action or written response.
If
you have any questions about the information in this notice, please contact one
of the technical contacts listed below or the appropriate NRR project manager.
Charles E. Rossi,lrector
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: T. E. Conlon, RII
(404) 331-5537
N. Merriweather, RII
(404) 331-5577 Attachments:
1. EGS Letter to NRC dated 1/2/90, Enclosing
Product Bulletin 90-1:
Recent Events
Concerning Patel Conduit Seils
- t
2. List of Recently Issued NRC Information Notices
"I0UI4 iN
O AND AMMD WMCWNOO0
Attachment 1 IN 90-23
April 4, 1990 January 2, 1990
U.S. Nuclear Regulatory Commission
101 Marietta Street NW
Suite 2900
Atlanta, GA
30323 Attn: Mr. Norman Merriweather
Gentlemen:
In accordance
with our
telephone conversation this morning, we
are
enclosing a copy of EGS Product Bulletin 90-1, "Recent Events Concerning
Patel Conduit Seals, P/N 841206", dated November 7, 1989.
Copies of
the
product bulletin were
sent
to our
utility customers both
by way of
Facsimile and U.S.
Mail.
Subsequently, we
followed
up with personal
telephone calls to each utility's EQ personnel.
The utilities/sites that
have purchased the Patel conduit seal are listed below:
UTILITY
PLANT SITE
Duquesne Light
Carolina Power & Light
Baltimore Gas & Electric
Nebraska Public Power District
Toledo Edison
Omaha Public Power District
Systems Energy Resources, Inc.
Georgia Power Co.
Wisconsin Public Service
Philadelphia Electric
Northern States Power
Consumers Power
Long Island Lighting Co.
Virginia Electric Power Co.
General Public Utilities
Public Service of Colorado
Beaver Valley
Harris/Robinson/Brunswick
Calvert Cliffs
Cooper
Davis Besse
Ft. Calhoun
Grand Gulf
Hatch/Vogtle
Kewaunee
Peach Bottom/Limerick
Monticello
Palisades
Shorehan
Surry
Oyster Creek
Ft. St. Vrain
Please contact us if you need further information.
We would appreciate
the
opportunity
to provide further inputs, especially concerning any notices or
information to be disseminated to the nuclear industry.
Sincerely, Gary J.,El
Productd irector
EGS Corporation 2 150 West Park Loop 2 Suite 301 ? Huntsville, Alabama 35806 = (205) 722-8500 - FAX (205) 722-8533 Knoxville Office c 408 Cedar Bluff Road cSuite 230 2 Knoxville, Tennessee 37923 c (615) 690-6200
F
FAX (615) 690-5423
fEEs
tIMC/I~uhpie AA
D
AD
UNGD
tCJW
Attachment 1
IN 90-23
April 4, 1990 MEMORANDUM
TM.
Patel/EGS Customers
FROM'
nary
Elam, Products Director, EGS Corp
SUBJEC1S
DATE.
Product Bulletin 90-1:
Recent Events Concerning Patel
Conduit Seals, P/N 841206
November 7, 1989
i
Grommet Use Rangey
The Patel Conduit Seal was originally supplied starting in 1985.
The
installation instructions were supplied as Patel Drawing A-N-841206-8, Rev. 0 which specified the following:
GRO
MAXIMUM INSULATION DIAMETER (IN.)
GR-12 GR-14 GR-16 GR-18
.170
.150
.135
.120
Implied within these specified maximum diameters is a use range for each
grommet .
Revision E, 3/6/87, of Patel Drawing A-N-841206-8 formally
specified the use range as follows:
GROMMET
NOMINAL USE RANGE:
INSULATION DIAMETER (IN.)
GR-12
.150 - .170
GR-14
.135 - .150
GR-16
.115 - .140
GR-18
.095 - .115 EGS Corporation = 150 West Park Loop , Suite 301 = Huntsville, Alabama 35806 = (205) 722-85002 FAX (205) 722-8533 Knoxville Office 2 408 Cedar Bluff Road:2 Suite 230 = Knoxville, Tennessee 37923 = (615) 690-6200 = FAX (615) 690-5423
Attachment 1
WMORNDUMIN
90-23 MEMORANDUJM
April 4, 1990
November 7, 1989 Page Two
Through discussions this week with one of our customers and the NRC, it
has been brought to our attention that wires with diameters smaller than
those specified have been utilized.
Our experience with the Patel Conduit
Seal indicates that a slightly undersized wire will not degrade the sealing
function.
For instance, Specimen P-1 in Report PEI-TR-841203-12, Rev. A
utilized a GR-16 grommet with wires ranging from .110 to .115 diameter
(.005 below the use range).
The insulation diameter of all wires to be sealed should be measured or
otherwise verified prior to the selection of the grommet size.
The grommet
part numbers (GR-12, GR-14, etc.) do not necessarily correspond with wire
gauge , i.e., a 16 AWG wire may require the use of a GR-18 grommet .
If
further help is required, consult with EGS Products personnel at 205/722-
8500.
In the near future, EGS intends to investigate and possibly extend the
grommet use range.
Loosening of Union Nuts:
At the same utility, the torque on the conduit seal union nuts was verified.
One of ninety conduit seals was found to have a significantly loose union
nut.
In approximately
half of the ninety
seals, the nut moved
approximately 1/4 inch when 50 ft.-lb. torque was applied.
This does not
indicate a degraded seal.
As a precaution, at a convenient time, we
recommend
that all conduit
seal
users
verify
the torque
on
a
representative sample of installed conduit seals.
To verify torque , attempt
to tighten the union nut first at a 40 ft-lb. wrench setting, then at a 50 ft.-
lb. setting.
If the nut doesn't move, it can be concluded that the 50 ft.-lb.
torque is intact.
Be sure to hold the 2 housing halves with pipe wrenches
so as not to disturb or over-torque other joints or electrical device
housings which may be connected to the conduit seal.
gA,,gIa/n.
AMADAWNCID
P Fj.ObMOGF
MEMORANDUM
November 7, 1989
Page TIhree
Attachment 1
IN 90-23
April 4, 1990 Conclusion
We do not believe these conditions are a serious concern in that some
slight variation in wire diameters and union nut torque should not degrade
the sealing function.
All users should be aware of conduit seal use ranges
and torque requirements.
If there is reason to believe that use ranges and
torques are not consistent with our installation procedures, we recommend
a review of your installation procedures and installed configurations.
We
encourage you to seek our inputs.
We are in the process of revising the
conduit seal installation procedure drawing, A-N-841206-8, to include
specific instructions to measure wire diameters.
The drawing will be
forwarded soon.
This bulletin was prepared as a service to our customers
to provide accurate information concerning the conduit seal.
Should you
have further questions, please contact Gary Elam or Johnny Jenkins at
205/722-8500.
zEs
5 IN6AWRIfIU, AN#APWNMCIR
YON40 06?
.
I
.
Attachment 2
IN 90-23
April 4, 1990 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
90-22
90-21
90-20
90-19
90-18
90-17
89-59, Supp. 2
90-16
Unanticipated Equipment
Actuations Following
Restoration of Power
to Rosemount Transmitter
Trip Units
Potential Failure of Motor-
Operated Butterfly Valves
to Operate Because Valve
Seat Friction was Under- estimated
Personnel Injuries Resulting
from Improper Operation of
Radwaste Incinerators
Potential Loss of Effective
Volume for Containment
Recirculation Spray at
PWR Facilities
Potential Problems with
Used on Diesel Generator
Air Start Receiver Tanks
Weight and Center of
Gravity Discrepancies
for Copes-Vulcan Valves
Suppliers of Potentially
Misrepresented Fasteners
Compliance with New
Decommissioning Rule
3/23/90
3/22/90
3/22/90
3/14/90
3/9/90
3/8/90
3/7/90
3/7/90
All holders of OLs
or CPs for nuclear
power reactors.
All holders of OLs
or CPs for nuclear
power reactors.
All NRC licensees
who process or
incinerate radio- active waste.
All holders of OLs
or CPs for PWRs .
All holders of OLs
or CPs for nuclear
power reactors.
All holders of OLs
or CPs for nuclear
power reactors.
All holders of OLs
or CPs for nuclear
power reactors.
All materials licensees.
OL = Operating License
CP = Construction Permit
list Information Notice 1990-01, Importance of Proper Response to Self-Identified Violations by Licensees (12 January 1990 , Topic : Notice of Violation , Uranium Hexafluoride )Information Notice 1990-02, Potential Degradation of Secondary Containment (22 January 1990 )Information Notice 1990-03, Malfunction of Borg-Warner Bolted Bonnet Check Valves Caused by Failure of the Swing Arm (23 January 1990 , Topic : Liquid penetrant )Information Notice 1990-04, Cracking of the Upper Shell-to-Transition Cone Girth Welds in Steam Generators, (26 January 1990 , Topic : Nondestructive Examination , Thermal fatigue )Information Notice 1990-05, Inter-System Discharge of Reactor Coolant (29 January 1990 )Information Notice 1990-06, Potential for Loss of Shutdown Cooling While at Low Reactor Coolant Levels (29 January 1990 , Topic : Reactor Vessel Water Level )Information Notice 1990-07, New Information Regarding Insulation Material Performance and Debris Blockage of PWR Containment Sumps (30 January 1990 )Information Notice 1990-08, KR-85 Hazards from Decayed Fuel (1 February 1990 )Information Notice 1990-08, KR-85 Hazards From Decayed Fuel (1 February 1990 )Information Notice 1990-09, Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licensees (5 February 1990 , Topic : Decommissioning Funding Plan , Uranium Hexafluoride )Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990 , Topic : Boric Acid , Hydrostatic , Stress corrosion cracking , Liquid penetrant )Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990 , Topic : Boric Acid , Hydrostatic , Nondestructive Examination , Stress corrosion cracking , Liquid penetrant )Information Notice 1990-11, Maintenance Deficiency Associated with Solenoid-Operated Valves (28 February 1990 )Information Notice 1990-12, Monitoring or Interruption of Plant Communications (28 February 1990 )Information Notice 1990-13, Importance of Review and Analysis of Safeguards Event Logs (5 March 1990 )Information Notice 1990-14, Accidental Disposal of Radioactive Materials (6 March 1990 , Topic : Brachytherapy )Information Notice 1990-15, Reciprocity Notification of Agreement State Radiation Control Directors Before Beginning Work in Agreement States (17 March 1990 , Topic : Uranium Hexafluoride )Information Notice 1990-16, Compliance with New Decommissioning Rule (7 March 1990 , Topic : Uranium Hexafluoride )Information Notice 1990-17, Weight and Center of Gravity Discrepancies for Copes-Vulcan Valves (8 March 1990 , Topic : Earthquake )Information Notice 1990-18, Potential Problems with Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990 )Information Notice 1990-18, Potential Problems With Crosby Safety Relief Valves Used on Diesel Generator Air Start Receiver Tanks (9 March 1990 )Information Notice 1990-19, Potential Loss of Effective Volume for Containment Recirculation Spray at PWR Facilities (14 March 1990 )Information Notice 1990-20, Personnel Injuries Resulting from Improper Operation of Radwaste Incinerators (22 March 1990 )Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction was Underestimated (22 March 1990 )Information Notice 1990-21, Potential Failure of Motor-Operated Butterfly Valves to Operate Because Valve Seat Friction Was Underestimated (22 March 1990 )Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units (23 March 1990 , Topic : Reactor Vessel Water Level )Information Notice 1990-23, Improper Installation of Patel Conduit Seals (4 April 1990 )Information Notice 1990-24, Transportation of Model Spec 2-T Radiographic Exposure Device (10 April 1990 , Topic : Exclusive Use )Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990 , Topic : Exclusive Use )Information Notice 1990-25, Loss of Vital AC Power With Subsequent Reactor Coolant System Heat-Up (16 April 1990 )Information Notice 1990-25, Loss of Vital AC Power with Subsequent Reactor Coolant System Heat-Up (16 April 1990 )Information Notice 1990-26, Inadequate Flow of Essential Service Water to Room Coolers and Heat Exchangers for Engineered Safety-Feature Systems (24 April 1990 )Information Notice 1990-27, Clarification of the Recent Revisions to the Regulatory Requirements for Packaging of Uranium Hexafluoride (UF6) for Transportation (30 April 1990 , Topic : Uranium Hexafluoride )Information Notice 1990-28, Potential Error In High Steamline Flow Setpoint (30 April 1990 )Information Notice 1990-28, Potential Error in High Steamline Flow Setpoint (30 April 1990 )Information Notice 1990-29, Cracking of Cladding and Its Heat-Affected Zone in the Base Metal of a Reactor Vessel Head (30 April 1990 , Topic : Nondestructive Examination , Liquid penetrant )Information Notice 1990-30, Ultrasonic Inspection Techniques for Dissimilar Metal Welds (1 May 1999 , Topic : Intergranular Stress Corrosion Cracking , Dissimilar Metal Weld , Exclusive Use )Information Notice 1990-31, Update on Waste Form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990 , Topic : Process Control Program )Information Notice 1990-31, Update on Waste form and High Integrity Container Topical Report Review Status, Identification of Problems with Cement Solidification, and Reporting of Waste Mishaps (4 May 1990 , Topic : Process Control Program )Information Notice 1990-32, Surface Crack and Subsurface Indications in the Weld of a Reactor Vessel Head (3 May 1990 )Information Notice 1990-33, Sources of Unexpected Occupational Radiation Exposures at Spent Fuel Storage Pools (9 May 1990 , Topic : Overexposure )Information Notice 1990-34, Response to False Siren Activations (10 May 1990 , Topic : Siren )Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990 , Topic : Siren )Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990 , Topic : Siren )Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990 , Topic : Authorized possession limits , Stress corrosion cracking )Information Notice 1990-39, Recent Problems with Service Water Systems (1 June 1990 )Information Notice 1990-40, Results of NRC-Sponsored Testing of Motor-Operated Valves (5 June 1990 , Topic : Weak link , Siren )Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990 , Topic : Siren )Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990 , Topic : Loss of Offsite Power , Siren )Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990 )... further results