Cracked Insertion Rods on Troxler Model 3400 Series Portable Moisture Density GaugesML031060065 |
Person / Time |
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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, Three Mile Island, 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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
09/26/1996 |
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From: |
Cool D NRC/NMSS/IMNS |
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To: |
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References |
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IN-96-052, NUDOCS 9609200181 |
Download: ML031060065 (14) |
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Similar Documents at 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, Three Mile Island, 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 |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 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 [[:Three Mile Island]] 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]] </code>.
[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 [[:Three Mile Island]] 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]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 September 26, 1996 NRC INFORMATION NOTICE 96-52: CRACKED INSERTION RODS ON TROXLER
MODEL 3400 SERIES PORTABLE MOISTURE
DENSITY GAUGES
Addressees
All U.S. Nuclear Regulatory Commission portable gauge licensees and vendors.
Purpose
NRC is issuing this information notice to alert addressees to the potential for cracks to develop
in the insertion rod of Troxler model 3400 portable moisture density gauges. If not detected
early, the cracks may propagate, eventually leading to complete failure of the insertion rod and
release of the contained radioactive material. This notice provides information that users of
these gauges may consider to avoid crack initiation and to detect existing cracks. It is expected
that recipients will review the information for applicability to their licensed activities and consider
actions, as appropriate, to avoid similar problems. However, suggestions contained in this
information notice are not NRC requirements; therefore, no specific action nor written response
is required.
Description of Circumstances
NRC was notified of several incidents where the source cup of a Troxler model 3401 portable
moisture density gauge separated from its insertion rod, releasing the contained, nominal 333 MBq (9.0 mCi), cesium-137, sealed source. One of the users of a failed gauge contacted the
manufacturer and requested an.examination of its failed gauge and all other Troxler gauges it
possessed. The examination determined that the failure occurred in the vicinity of the weld
joining the stainless steel insertion rod and source cup and that several other gauges in the
user's possession were suspected of containing cracked rods/cups, as well. The manufacturer
recommended that the user discontinue use of all gauges suspected of being damaged until
further inspection.
Following examination of the users gauges, the manufacturer initiated an inspection and testing
program on model 3400 series gauges returned to it for disposal or repair that contained
unthreaded" (not joined with a threaded connection) source cups and insertion rods. This
included only gauges with serial numbers less than 13301. The manufacturer only examined
gauges with unthreaded" rods/cups because all gauges that were reported as having cracks
were this configuration. The manufacturer provided the following information and results from
its investigation:
235 gauges that had been returned for repair and 75 gauges that had been returned for
disposal were inspected.
9609200181 .LUb(t LiIL/
Jo
0 IZ~e4a TrE 4&go11(o
IN 96-52 September 26, 1996 * Drop and bending tests were performed on the 75 gauges that had been returned
for
disposal to determine the force necessary to cause failure of the weld joint.
Fatigue was
not considered during the testing.
- Two of the 75 gauges returned for disposal were determined to contain a transverse
crack on the insertion rod in the weld region.
- A number of the rod/cup welds of the 235 gauges returned for repair were determined
be 'unusual, but none were determined to contain cracks. to
- The manufacturer received a report of another gauge, not included in the investigation, whose rod/cup joint had also failed completely in the field, releasing the contained
sealed source. The manufacturer suspected that the gauge had been abused
during
use, but the gauge was not available for the manufacturer to perform a full
examination.
Based on the results of its investigation, the manufacturer concluded that weld
failure is an -
unlikely event when the gauge is subjected to nornal conditions of use and
accident conditions. It also concluded that fatigue and thermal stresses would typical drop)
not be expected
to have an adverse effect on the weld joint under normal conditions. However, fatigue nor thermal testing during its investigation. there was no
Concurrent with the manufacturer's investigation, NRC contracted an independent
testing facility to examine, in detail, the failed gauge, previously examined by third-party
the manufacturer, and four other of the users model 3400 series gauges (three of which were
suspected of also
being damaged), and determine the root cause of the failure, if possible.
resulted in a number of conclusions and observations, including: This examination
- The failure resulted from an initial crack in the weld region of the insertion rod
that
progressively until it failed completely in a brittle manner, releasing the contained grew
sealed
source.
- The initial transverse crack likely resulted from the insertion rod being subjected
to a
severe bending load (possibly an impact) not sufficient to cause catastrophic
brittle
failure.
- The initial crack propagated slowly due to repeated loads during use. The
crack
extended approximately 2900 before the final brittle fracture.
- The region of crack initiation (the heat-affected zone around the weld) was very
hard, but
the weld was very soft. This differential in hardness was caused by material
selection, joint configuration, and the welding procedure, and provided a stress concentration
the region around the weld. The stress concentration made the weld area in
more
susceptible to crack initiation in a high-bending load condition.
- One of the other gauges received from the licensee was confirmed to contain
transverse crack in the region of the weld. Hardness testing indicated that a
this gauge
also contained a soft weld and a high-hardness region surrounding the weld.
In
addition, the rod/cup was constructed using the same materials and processes
as the
failed gauge.
IN 96-52 September 26, 1996 * The remaining three other gauges were undamaged, but had similar hardness
characteristics as the failed gauge.
- All gauges received for testing contained "unthreaded" rods/cups and were constructed
using the same materials and processes. The source cups on newer model 3400 series
gauges (serial numbers above 13300) are threaded to the insertion rod before joining by
welding.
- The weld configuration of the rod/cup connection Is not optimum for its intended
application, and provides a high stress concentration in the weld area. An alternate
selection of materials and joint configuration, and a post-heat treatment may have
reduced the high-hardness region, resulting in a lower stress concentration in the weld
area.
Based on the above observations and testing performed, the third-party contractor concluded
that all gauges manufactured in the same manner as the failed gauges would be susceptible to
crack initiation when subjected to a severe bending load. In addition, the contractor concluded
that a crack on this type of gauge would be expected to propagate slowly over time and could
be easily detected visually, either by using a dye penetrant evaluation technique or by observing
the weld area under magnification. The contractors visual examination without dye penetrant or
magnification indicated a potential crack in an insertion rod,' that was subsequently determined
to only be a surface feature. Therefore, visual examination should not be considered a reliable
way to identify cracks.
The figure below shows the typical configuration of a Troxler model 3400 series gauge and the
locations of the insertion rod, source cup, and weld:
Weld Source Cup
Typical Model 3400 Series Gauge
IN 96-52 September 26, 1996 In June 1996, Troxler issued a bulletin (attached) discussing the above
incidents and the results
of its investigation. The bulletin provided gauge users with three recommendations
reduce the likelihood of future'source cup detachment incidents. These on how to
included:
1. Gauges should be used in accordance with the manufacturer's instructions
operator's manual. Under no circumstances should the insertion rod found in the
ever be driven or
forced into the test material. A drill rod accessory is provided with
the gauge to prepare
a hole in the test material Into which the rod is inserted. If the user
purchases
gauge that does not include the drill rod accessory, the user should contact a used
manufacturer to obtain a replacement drill rod. the
2. Users should have the gauge and insertion rod inspected at least once
every 5 years for
unusual wear and tear.
3. Companies purchasing used gauges should require an inspection
before purchase.
Gauges involved in accidents should be inspected before further use.
Discussion
The aforementioned observations and investigations indicate that a
gauge manufactured using
the same materials, welding process, and rod/cup configuration as
those identified as'
containing cracks would be expected to be susceptible to crack initiation
when placed in a high-bending load. Cracks in the weld region of the in the weld region
insertion rods would be
expected to propagate over time, possibly leading to complete failure
contained sealed source. However, before complete failure, a crack and release of the
of
identifiable by macroscopic visual examination or dye-penetrant testing. this type should be
crack initiation could occur under other conditions not discussed here It is unknown whether
nor considered during the
testing performed by the manufacturer or the third-party contractor.
When used according to the manufacturer's instructions and recommended
crack initiation would not be expected. Users of Troxler model 3400 conditions of use, series gauges, and other
similar gauges, should always operate their devices in accordance with
the manufacturers
instructions and under the recommended conditions of use, and should
insertion rod in a bending-load condition. The bending-load force necessary never place the
was not determined during either the manufacturer's or the third-party to initiate a crack
investigations. Therefore, bending-loads on the insertion rod, other contractor's
than those encountered
during normal use, should be avoided.
The manufacturer has changed the design, materials, and manufacturing
3400 series gauges several times since their introduction. The manufacturer's process for model
contractor's investigations were limited to model 3400 series gauges and third-party
with serial numbers less
than 13301 (gauges with Nunthreaded* rods/cups and the same materials
construction). Therefore, the susceptibility to crack initiation of gauges and methods of
with "threadedn
rods/cups or with other materials of construction and welding processes
(models with serial
numbers greater than 13300) is not known. However, all failed gauges
to
numbers less than 13301. A threaded rod/cup connection may provide date have had serial
of safety even if a crack began and led to complete failure, as the an additional measure.
source cup would likely still
need to be unthreaded from the rod to release the contained sealed
source.
K>
IN 96-52 September 26, 1996 Based on the results of the manufacturers and the third-party contractor's Investigations, and
the recommendations made in Troxier's bulletin, users of Troxler model 3400 series gauges
with serial numbers less than 13301 are encouraged to have their gauges inspected for cracks
in the weld area of the insertion rod. In addition, it is recommended that these gauges be
rechecked for cracks on at least a 5 year basis (more or less frequently depending on use level
and conditions). It is further recommended that users of model 3400 series gauges with serial
numbers 13301 and above also have their insertion rods checked for cracks in the weld area
and consider periodic re-inspection, as well.
Inspections of insertion rod weld areas should only be performed by persons qualified to
conduct an appropriate nondestructive examination (NDE) for macroscopic cracks (e.g., visual
examination with magnification or dye penetrant) and licensed to handle the contained
radioactive material. Visual examinations without magnification and examinations by
unqualified persons are not recommended, as these could lead to inaccurate results and
unnecessary doses to persons performing the examination. Persons who possess Troxler
model 3400 series gauges who wish to have their insertion rods inspected should contact either
the manufacturer or an NDE inspector qualified to perform the inspection. For guidance on
finding qualified NDE inspectors, licensees may contact the Technical Services Division of the
American Society for Nondestructive Testing, Inc., at (800) 222-2768 or the Non-Destructive
Testing Management Association at (800) 317-0822.
Users who determine that their gauge's insertion rod contains a crack should immediately stop
using the gauge and notify the manufacturer. Repair or replacement of cracked insertion rods
should only be performed by qualified persons, authorized by license to perform these activities.
The manufacturer or other licensee authorized to performed the repair or replacement will
indicate the manner in which the gauge should be returned for service.
The incidents and investigations discussed in this notice also demonstrate the need to
determine the appropriate weld material, configuration, and processes for a particular use
application when designing gauges of this type. The choice of weld specifications should be
based on the requirements of the gauge during normal and accident conditions of use that it Is
likely to encounter during its working life. It is imperative that manufacturers identify these likely
conditions as best as possible and design their gauges accordingly. Although the choice of
weld material, configuration, and processes for model 3400 series gauges with serial numbers
below 13301 appears to be sufficient under normal conditions of use, it appears to provide a
means by which a crack could begin in the weld area if subjected to higher than normal bending
loads.
IN 96-52 September 26, 1996 This information notice requires no specific action nor written response.
If you have any
questions about the information in this notice, please contact the technical
contact listed below
or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Douglas Broaddus, NMSS
(301) 415-5847 E-mail: dab@nrc.gov
Attachments:
1. Troxder Bulletin Issued June 1996
2. Ust of Recently Issued NMSS Information Notices
3. Ust of Recently Issued NRC Information Notices
Attachment 1 IN 96-52 September 26, 1996 Page 1ofI
As a result of several recent incidents that have occurred in which the source cup has
become detached from the extendable source rod of Troxler 3400 series gauges, Troxler is issuing this bulletin to assist users of surface/moisture gauges in using the
gauges safely in compliance'with the manufacturer's instructions. Troxler anticipates
that this bulletin will help prevent additional source cup detachment incidents.
In order to simpli* the manufacturing process, and not due to any incident,
3400 series gauges with serial numbers 13,300 and greater (i.e., manufactured since
mid-1986) rely on a combination of a weld and a threaded design to secure the source
cup to the source rod. With the addition of threads, the source cups will not dislodge
unless the cups are physically unscrewed from the rod. The cases involving detached
cups occurred with serial numbers below 13,300 which did not incorporate the
threaded design and rely on the weld.
Upon notification of the above incidents, the Troxler Research and
Development Department initiated an inspection program for gauges received for
service and disposal. This inspection program looked at 310 gauges, 235 received for
service and 75 received for disposal. No cracked rods were found in the gauges
received for service. In the group of disposal gauges, two rods were identified as
having a crack approximately 40% around the circumference. Further evaluation of
these two rods demonstrated that they would not fail in normal use or typical accident
conditions in the environment in which they are used. Several thousand gauges have
been inspected over the last two years. Based on this inspection program Troxler has
seen no signs of manufacturing defects. Inspections have revealed some cases of abuse
of the equipment.
In an effort to reduce the likelihood of future source cup detachment incidents, Troxier, in cooperation with the North Carolina Division of Radiation-Protection, has
drafted several recommendations for gauge users as follows:
1. Gauges should be used in-accordance with manufacturer's instructions found
in the accompanying operator's manual. Under no circumstances should the source
rod ever be driven or forced into the test material. A drill rod accessory is provided
with the gauge to prepare a hole in the test material into which the source rod is
inserted. If the user purchased a used gauge from someone other than Troxler which
does not include the accessory, the user should contact Troxler to obtain a drill rod.
2. Troxler recommends that the user return the gauge to the manufacturer at
least once every five years to allow the manufacturer to inspect the gauge and source
rod for unusual wear and tear.
3. Troxler recommends that companies purchasing used gauges require an
inspection by the manufacturer prior to purchase. Troxler takes no position regarding
gauge inspections and source rod evaluations performed by anyone other than
authorized Troxier Service Centers. Troxler recommends that any gauge involved in
an accident be returned to the manufacturer for inspection prior to further use.
For further information, contact Michael Dishman, the Troxler Corporate Radiation
Safety Officer, at (919) 549-8661.
Issued June 1996
GIoAQ
Attachment 2 IN 96-52 September 26, 1996 Page 1 of I
UST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
-51 Residual Contamination 09111/96 All material licensees
Remaining in Krypton-85 Handling System After
Venting
98-47 Recordkeeping, Decommis- 08/19/96 All U.S. Nuclear Regulatory
sioning Notifications for Commission licensees
Disposals of Radioactive
Waste by Land Burial
Authorized Under Former
10 CFR 20.304,20.302, and Current 20.2002
96-35 Failure of Safety Systems 06/11/96 All U.S. Nuclear Regulatory
on Self-Shielded Irradia- Commission Irradiator
tors Because of Inadequate licensees and vendors
Maintenance and Training
633 Erroneous Data from Defec- 05/224/96 All material and fuel cycle
tive Thermocouple Results licensees that monitor tem- in a Fire perature with thermocouples
96-28 Suggested Guidance Relat- 05/01/96 All material and fuel cycle
ing to Development and licensees
Implementation of Correc- tive Action
96-21 Safety Concerns Related 04110/96 All NRC Medical Ucensees
to the Design of the Door authorized to use brachy- Interlock Circuit on therapy sources in high- Nucletron High-Dose Rate and pulsed-dose-rate remote
and Pulsed Dose Rate
Remote Afterloading Brachy- therapy Devices
96-20 Demonstration of Associ- 04/04/96 All industrial radiography
ated Equipment Compliance licensees and radiography
with 10 CFR 34.20 equipment manufacturers
96-18 Compliance With 10 CFR 03/25X96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed form
Attachment 3 IN 96-52 September 26, 1996 Page 1 of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
92-68, Potentially Sub-standard 09/16196 All holders of OLs or CPs
Supp. 1 Slip-On, Welding Neck, for nuclear power reactors
and Blind Flanges
96-51 Residual Contamination 09/111/96 All material licensees
Remaining in Krypton-85 Handling System After
Venting
96-50 Problems with 09104/96 All holders of OLs and CPs
Levering-In Devices for nuclear power plants
in Westinghouse
Circuit Breakers
96-49 Thermally Induced 08/20/96 All holders of OLs or CPs
pressurization of Nuclear for nuclear power reactors
Power facility Piping
96-48 Motor-Operated Valve 08121196 All holders of OLs or CPs
Performance Issues for nuclear power reactors
96-47 Recordkeeping, Decommis- 08/19/96 All U.S. Nuclear Regulatory
sioning Notifications for Commission licensees
Disposals of Radioactive
Waste by Land Burial
Authorized Under Former
10 CFR 20.304, 20.302, and Current 20.2002
96-46 Zinc Plating of Hardened 08/12/96 All holders of OLs or CPs
Metal Parts and Removal for nuclear power reactors
of Protective Coatings in
Refurbished Circuit Breakers
96-45 Potential Common-Mode 8/12196 All holders of OLs or CPs
Post-Accident Failure of for nuclear power reactors
Containment Coolers
OL = Operating License
CP = Construction Permit
Vendor List for Portable Moisture Density Gauges
Boart Longyear Company
CPN Products
2830 Howe Rd.
Martinez, CA 94533 Campbell Security Equipment Co. (CESCO)
2500 Annalisa Dr.
Concord, CA 94520
Humboldt Scientific, INC
553E Pylon Dr.
Raleigh, NC 27607
Ohmart Corp.
4241 Allendorf Dr.
Cincinnati, OH 45209
Seaman Nuclear Corp.
3846 West Wisconsin Av.
Milwaukee, WI 53208
Texas Nuclear Products
TN Technologies, INC
2555 North IH-35, P.O. Box 800
Round Rock, TX 78680-0800
Troxler Electronic Labs, INC
3008 Comwallis Rd.
P.O. Box 12057
Research Triangle Park, NC 27709
J1 IN 96-52 September 26, 1996 This information notice requires no specific action nor written response. If you have any
questions about the information in this notice, please contact the technical contact listed below
or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
, Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Douglas Broaddus, NMSS
(301) 415-5847 E-mail: dab@nrc.gov
Attachments:
1. Troxler Bulletin Issued June 1996
2. List of Recently Issued NMSS Information Notices
3. List of Recently Issued NRC Information Notices
At&AYcfs ;ePs
a. z7cktr
DOCUMENT NAME: 96-52.IN
See previous concurrence
To receive acopy of this document. Indicate hIthe box: *v a Copy fthoud aftchmentenckoure T a Copy vlh ettacumentonclosur vW v No cowy
NAME DBroaddus I-Camper EKraus JPiccone DCool
DATE 8/26196 8/29/96 8/26/96 9/10/96 9/16/96 OFFICIAL RECORD COPY
IN 96-XX
September , 1996 This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate regional office.
Donald A. Cool, Director
- Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Contact: Douglas Broaddus, NMSS
(301) 415-5847 E-mail DAB@NRC.GOV
Attachments:
1. Troxler Bulletin issued June 1996
2. List of Recently issued NMSS Information Notices
3. List of Recently issued NRC Information Notices
DOCUMENT NAME: C:\WPDOCS\GENERIC.COM\TROXLER.IN2
Toreceive a copy of tWie document. Indicate In the box: C'- Copy without attachment/enclosure 'E Copy with attachmontjenloesur ND No copy
OFFICE IMAB EIMAB Tech Editor L-i7 LI
NAME DBroaddus** LCamper** EKraus*- iPccone D--
DATE 8/26/96 8/29/96 8/26/96 * ///96C/96 OFFICIAL RECORD COPY
IN 96-XX
September , 1996 This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Contact: Douglas Broaddus, NMSS
(301) 415-5847 E-mail DAB@NRC.GOV
Attachments:
1. Troxler Bulletin issued June 1996
2. List of Recently issued NMSS Information Notices
3. List of Recently issued NRC Information Notices
DOCUMENT NAME: C:\WPDOCS\GENERIC.COM\TROXLER.IN2
To Dscelve a copy of thi document, Indcate In the box: 'C
- Copy without attchrnent/enoloure 'E' - Copy with gttachmrent/enclasure N - No copy
OFFICE- IMAB E IMAB Tech Editor N E I
INAME DBroaddus** LCamper** EKraus* Liccone ID H
DATE 8/26/96 8/29/96 8/26/96 __ /_ I96/It /96M
OFFICIAL RECORD COPY
UNITED STATES
NUCLEAR REGULATORY COMMISSION FIRST CLASS MAIL
WASHINGTON, D.C. 20555-0001 POSTAGE AND FEES PAID
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
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