Transportation of Model Spec 2-T Radiographic Exposure DeviceML031210569 |
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, 07109056, 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: |
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) |
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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, 07109056, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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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 [[:07109056]] 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 [[:07109056]] 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 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
the NRC Certificate of Compliance No. 9056, which imposes more restrictive in
requirements for proper transportation of the model SPEC 2-T radiographic
exposure device.
It is suggested that licensees review this information for applicability
operations involving transportation of radiography devices, and distributeto
it to persons responsible for proper transport of devices. However, notice does not constitute new NRC requirements, and no written response this
required. is
Description of Circumstances
A certificate of compliance is issued by the NRC when a specific package
the requirements of 10 CFR Part 71 and is approved by the NRC for meets
radioactive material. Conditions for proper transportation of transport 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
the U.S. Department of Transportation and 10 CFR Part 71 of the Commission's of
Regulations for the transportation of radioactive materials.
Prior to this recent change, the COC specified that for transportation
than 110 curies of iridium-192, the radiographic exposure device of more
be within a protective overpack or transported by exclusive use must either
accordance with the requirements of 49 CFR 173.441(b). The shipment in
purpose for this
condition was to assure that the radiation dose rate on the surfaces
radiographic exposure device or its overpack did not exceed 200 of the
hour. millirem per
PR I¢
POg q0 0f1101
4dzAi_0
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. maximum
Apparently, the radiation measurements used to determine the 110 curie device
between the surface of the
activity were not corrected for the distance cor- and the effective center of the radiation measurement instrument. This
rection was because of the small dimensions of the model SPEC 2-T depleted
uranium shield.
Discussion:
measure- The staff evaluated the information obtained from previous radiation maximum
ments and determined that the dose rates had been underestimated. The
to a surface dose rate
activity in the model SPEC 2-T device that corresponds conditions
of 200 millirem per hour is 45 curies of iridium-192. As a result, instead of
8 and 9 of the NRC's COC No. 9056 were amended to specify 45 curies was reduced
110 curies. Also, the maximum quantity of iridium-192 per package
from 240 curies to 225 curies.
COC
Users of the model SPEC 2-T device should be aware of the enclosed amended
also note that a radiation
No. 9056 issued on February 21, 1990. Users should radiation
survey must be made prior to each shipment to ensure that the external in
levels of the devices or the overpack do not exceed the limits specified
10 CFR 71.47, and 49 CFR 173.441.
NRC. If
This information notice does not require any written response to the NRC
you have any questions about this matter, please contact the appropriate
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
Personnel Injuries 03/22/90 All U.S. NRC licensees
90-20 who process or incinerate
Resulting from Improper
Operation of Radwaste radioactive waste
Incinerators
Compliance with New 03/07/90 All materials licensees
90-16 Decommissioning Rule
90-15 Reciprocity: Notification 03/07/90 All holders of NRC
of Agreement State Radiation materials licenses which
Control Directors before authorize use of radio- Beginning Work in Agreement active material at
States temporary job sites
Accidental Disposal of 03/06/90 All NRC Byproduct
90-14 Materials Licensees
Radioactive Materials
Extended Interim Storage of 02/05/90 All holders of NRC
90-09 materials licenses
Low-Level Radioactive Waste
by Fuel Cycle and Materials
Licensees
90-01* Importance of Proper 01/12/90 All holders of NRC
Response to Self-Identified materials licenses
Violations by Licensees
89-85 EPA's Interim Final Rule 12/15/89 All medical, academic, on Medical Waste Tracking industrial, waste
and Management 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 PAAWE
90bg l 6 l USA/9056/B(U) I 1 1 p
S. This te pacagi Jedonet desced hi Iem S below. 1ablO . nitd
" bf
tri hnwto si OCode
of Federal legulations, Part 71. Paciaglig and Transportation of RadioactivO Matea
b. This certifct does a ot mie onior trom Compliance with any Mwmmei
imeu td 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 m9MUM 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
accordance with 5(a)(3). * ' / --
package must be within a protective overpack as-described and constructed in
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 Improper Installation of 4/4/90 All holders of OLs
Patel Conduit Seals or CPs for nuclear
power reactors.
90-22 Unanticipated Equipment 3/23/90 All holders of OLs
Actuations Following or CPs for nuclear
Restoration of Power power reactors.
to Rosemount Transmitter
Trip Units
90-21 Potential Failure of Motor- 3/22/90 All holders of OLs
Operated Butterfly Valves or CPs for nuclear
to Operate Because Valve power reactors.
Seat Friction was Under- estimated
90-20 Personnel Injuries Resulting 3/22/90 All NRC licensees
from Improper Operation of who process or
Radwaste Incinerators incinerate radio- active waste.
90-19 Potential Loss of Effective 3/14/90 All holders of OLs
Volume for Containment or CPs for PWRs.
Recirculation Spray at
PWR Facilities
90-18 Potential Problems with 3/9/90 All holders of OLs
Crosby Safety Relief Valves or CPs for nuclear
Used on Diesel Generator power reactors.
Air Start Receiver Tanks
90-17 Weight and Center of 3/8/90 All holders of OLs
Gravity Discrepancies or CPs for nuclear
for Copes-Vulcan Valves power reactors.
89-59, Suppliers of Potentially 3/7/90 All holders of OLs
Supp. 2 Misrepresented Fasteners or CPs for nuclear
power reactors.
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: 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)
- 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)
- 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)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking (PWSCC) of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Liquid penetrant)
- Information Notice 1990-10, Primary Water Stress Corrosion Cracking of Inconel 600 (23 February 1990, Topic: Boric Acid, Hydrostatic, Nondestructive Examination, 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)
- 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)
- Information Notice 1990-24, Transportation of Model SPEC 2-T Radiographic Exposure Device (10 April 1990)
- 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)
- 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: Dissimilar Metal Weld)
- 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)
- Information Notice 1990-34, Response to False Siren Activations (10 May 1990)
- Information Notice 1990-35, Transportation of Type a Quantities of Non-Fissile Radioactive Materials (24 May 1990)
- Information Notice 1990-37, Sheared Pinion Gear-To-Shaft Keys in Limitorque Motor Actuators (24 May 1990)
- Information Notice 1990-38, License and Fee Requirements for Processing Financial Assurance Submittals for Decommissioning (6 November 1990, Topic: Authorized possession limits)
- 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)
- Information Notice 1990-41, Potential Failure of General Electric Magne-Blast Circuit Breakers and Ak Circuit Breakers (12 June 1990)
- Information Notice 1990-42, Failure of Electrical Power Equipment Due to Solar Magnetic Disturbances (19 June 1990)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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