Transportation of Model Spec 2-T Radiographic Exposure Device| ML031210569 |
| 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, 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, 07109056, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  |
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| Issue date: |
04/10/1990 |
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| From: |
Cunningham R NRC/NMSS/IMNS |
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| To: |
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| References |
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| IN-90-024, NUDOCS 9004040223 |
| Download: ML031210569 (6) |
|
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, 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, 07109056, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane |
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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 [[:07109056]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Crane]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555
April 10, 1990
NRC INFORMATION NOTICE NO. 90-24: TRANSPORTATION OF MODEL SPEC 2-T
RADIOGRAPHIC EXPOSURE DEVICE
Addressees
All NRC licensees authorized to use, transport, or operate radiographic
exposure devices and source changers.
Purpose
This information notice is provided to alert licensees of a recent change in
the NRC Certificate of Compliance No. 9056, which imposes more restrictive
requirements for proper transportation of the model SPEC 2-T radiographic
exposure device.
It is suggested that licensees review this information for applicability to
operations involving transportation of radiography devices, and distribute
it to persons responsible for proper transport of devices.
However, this
notice does not constitute new NRC requirements, and no written response is
required.
Description of Circumstances
A certificate of compliance is issued by the NRC when a specific package meets
the requirements of 10 CFR Part 71 and is approved by the NRC for transport of
radioactive material. Conditions for proper transportation of the model SPEC
2-T radiographic exposure device are stated in NRC certificate of compliance
(COC) No. 9056 (Attachment 1).
These conditions augment the requirements of
the U.S. Department of Transportation and 10 CFR Part 71 of the Commission's
Regulations for the transportation of radioactive materials.
Prior to this recent change, the COC specified that for transportation of more
than 110 curies of iridium-192, the radiographic exposure device must either
be within a protective overpack or transported by exclusive use shipment in
accordance with the requirements of 49 CFR 173.441(b). The purpose for this
condition was to assure that the radiation dose rate on the surfaces of the
radiographic exposure device or its overpack did not exceed 200 millirem per
hour.
POg
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IN 90-24 April 10, 1990 The NRC was informed that the surface dose rate on the radiography device
could exceed 200 millirem per hour when loaded with 110 curies of iridium-192.
Apparently, the radiation measurements used to determine the 110 curie maximum
activity were not corrected for the distance between the surface of the device
and the effective center of the radiation measurement instrument. This cor- rection was because of the small dimensions of the model SPEC 2-T depleted
uranium shield.
Discussion:
The staff evaluated the information obtained from previous radiation measure- ments and determined that the dose rates had been underestimated. The maximum
activity in the model SPEC 2-T device that corresponds to a surface dose rate
of 200 millirem per hour is 45 curies of iridium-192. As a result, conditions
8 and 9 of the NRC's COC No. 9056 were amended to specify 45 curies instead of
110 curies. Also, the maximum quantity of iridium-192 per package was reduced
from 240 curies to 225 curies.
Users of the model SPEC 2-T device should be aware of the enclosed amended COC
No. 9056 issued on February 21, 1990.
Users should also note that a radiation
survey must be made prior to each shipment to ensure that the external radiation
levels of the devices or the overpack do not exceed the limits specified in
10 CFR 71.47, and 49 CFR 173.441.
This information notice does not require any written response to the NRC. If
you have any questions about this matter, please contact the appropriate NRC
regional office or this office.
Richard E. Cunningham, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical Contact:
Steyen L. Baggett, NMSS
492-0542 Attachments:
1. NRC Certificate of Compliance
No. 9056.
2. List of Recent NMSS Information Notices.
3. List of Recent NRR Information Notices.
-.
-.
9
Attachment 2
IN 90-24
April 10, 1990 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
90-20
90-16
90-15
90-14
90-09
90-01*
89-85
Personnel Injuries
Resulting from Improper
Operation of Radwaste
Incinerators
Compliance with New
Decommissioning Rule
Reciprocity: Notification
of Agreement State Radiation
Control Directors before
Beginning Work in Agreement
States
Accidental Disposal of
Radioactive Materials
Extended Interim Storage of
Low-Level Radioactive Waste
by Fuel Cycle and Materials
Licensees
Importance of Proper
Response to Self-Identified
Violations by Licensees
EPA's Interim Final Rule
on Medical Waste Tracking
and Management
03/22/90
03/07/90
03/07/90
03/06/90
02/05/90
01/12/90
12/15/89
All U.S. NRC licensees
who process or incinerate
radioactive waste
All materials licensees
All holders of NRC
materials licenses which
authorize use of radio- active material at
temporary job sites
All NRC Byproduct
Materials Licensees
All holders of NRC
materials licenses
All holders of NRC
materials licenses
All medical, academic, industrial, waste
broker, and waste
disposal site licensees
- Correct Number tor 90-01 should be 90010145.
--
iON=
mc PrE asl
cmERTIFICATE OF COMPLIANCE
__
_
enR"
FOR RADIOACTM MATERIALS PACKAGES
ATTACHMENT 1
s.6vPA0CAO WN
P AAWE
90bg
l 6 l USA/9056/B(U)
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S. This
"
tri
nwto
te
pacagi
J edonet desced hi Iem S below. 1ablO
.
nitd
bf
s
h
i OCode
of Federal legulations, Part 71. Paciaglig and Transportation of RadioactivO Matea
b. This certifct does
ot
a
imeu
mie onior trom Compliance with any Mwmmei
t d le
gutations of li Ut Osps'tent Of Trfanportation or other
applicable regulatory gencisL
cuding go governme
of any ountry through or ito which lie Packag will be Irneportd.
S. THIS CEPIICATIE m9 MUM ON THE BASIS OfA SAFrT AALVSW REPOT OF THE PACKAUE8E)NJo aO APPUCATI O
a. UILU TO Mm &WAimi
6.11111 AND
WMIG&TIC11lO
OF REPORT OR APPUCATION:
Source Production and
Source Production and Equipment Company Inc.
Equipment Company, Inc.
application dated March 13, 1989 as supplemented.
113 Teal Street
St. Rose, LA 70087
.o
7I-9056
4. CON011`1IO1 This eeottfdcate is sodo
I
ontutfI* lieInents of IC cm Pet il.
apolable, VW li ocfduon g Ald
below.
(a) Packaging
(1) Model fso.:
SPEC 2-T
(2) Description
A steel encased, uranium shielded Gamma Ray Projector. Primary
components consist of an outer steel shell, internal bracing, depleted
uranium shield, and a Zircalloy OS" tube. The contents are securely
positioned in the Zircalloy *SO tube by a source cable locking device and
shipping plug. The unit resembles a rectangular box approximately 130
long by 4-S/88 high by 4-1/40 wide with a maximum gross weight of 49 pounds.
(3) Drawings
The packaging is constructed in accordance with Source Production and
Equipment Company Inc. Drawing Nos. 12688-1. Rev. (0); 788-1 Rev. (0);
and 788-2 Rev. (05.
The packaging may also be as shown in Source Production and Equipment
Company Drawing No. 1000, Rev (0) provided fabrication was completed
prior to June 8, 1989.
The overpack is a 12 gallon open head 20 or 22 gauge National Motor
Freight Classification 100-G, Item 260 steel drum constructed in
accordance with Source Production and Equipment Company, Inc. Drawing
No. 53189-2 Rev. (0).
(b) Contents
(1) Type and form of material
Iridium 192 as sealed sources which meet the requirements of special
form radioactive material.
- 4*4#53 SprP
'-S
comonnoNs (contkred)
U.S NUCLEAP RE£ULATC
'.
Page 2 - Certificate No. 9056 - Revision No. 6 - Docket No. 71-9056
(2) Maximum quantity of material per package
225 curies
6. The source must be secured in the shielded position of the packaging by the
shipping plug, source assembly, and locking device. The shipping plug and source
assembly used must be fabricated of materials capable of resisting a 14750F fire
environment for one-half hour and maintaining their positioning function. The
source assembly ball stop must engage the locking device. The flexible cable of
the source assembly and shipping plug must be of;sufficient length and diameter to
provide positive positioni g0 fhetsourice In tbe(gjuided position.
7. The nameplates must be 4fricated of materials capablie 6 resisting the fire test
of 10 CFR Part 71 and maintaining their legibility.
(W
B. For transportation'of more than 45 curies per package in private carriage the
shipment must belas accordance with 49 CFR 173.441(b). --,.2 A
v;
..
epackfge
bewa
9. For transportation of more than 45 curies per package beta common carrier, the
package must be within a protective overpack as-described and constructed in
accordance with 5(a)(3).
'
/
K
.--
10. The packaging authorized by this certificate is hereby approved for use under the
general license provisions of 10 CFR 171.12.
11. Expiration date: August 31, 1994.
REFERENCES
Source Production and Equipment Company,'Inc. application dated March 13, 1989.
Supplements dated:
July 6, August 21, and August 28, 1989.
-
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
Charles E. MacDonald, Chief
Transportation Branch
Division of Safeguards
and Transportation, NMSS
Date: FE
189
3
Attachment 3
IN 90-24
April 10, 1990 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
90-23
90-22
90-21
90-20
Improper Installation of
Patel Conduit Seals
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
4/4/90
3/23/90
3/22/90
3/22/90
3/14/90
3/9/90
3/8/90
3/7/90
All holders of OLs
or CPs for nuclear
power reactors.
All holders of OLs
or CPs for nuclear
power reactors.
All 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.
90-19
90-18
90-17
89-59, Supp. 2 OL = Operating License
CP = Construction Permit
|
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|
| 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)
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