Handling Uncontained Yellowcake Outside of a Facility Circuit| ML031060213 |
| 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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Crane  |
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| Issue date: |
12/06/1995 |
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| From: |
Greeves J NRC/NMSS/DWM |
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| To: |
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| References |
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| IN-95-055, NUDOCS 9511300301 |
| Download: ML031060213 (5) |
|
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, 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 [[: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. 20555-0001
December 6, 1995
NRC INFORMATION NOTICE 95-55: HANDLING UNCONTAINED YELLOWCAKE OUTSIDE OF A
FACILITY PROCESSING CIRCUIT
Addressees
All Uranium Recovery Licensees.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the hazards associated with the handling of
uncontained yellowcake (natural uranium) at uranium recovery facilities. It
is expected 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 are not
new NRC requirements; therefore, no specific action nor written response is
required.
Description of Circumstances
During a routine NRC inspection of an operating conventional uranium mill, the
inspector discovered that the licensee had used an unorthodox method for
drying yellowcake which could have resulted in significant airborne exposure
to workers. No worker received an internal exposure in excess of regulatory
limits because of the careful work practices and procedures used for this Job.
Fifteen barrels of yellowcake were stored outside for several months.
Inleakage through the barrel bung holes resulted in the contents becoming wet
and requiring re-drying before shipment. The licensee was unable to use the
conventional yellowcake drying circuit of the mill because of delays in
receiving a state permit to use this equipment; tferefore, the licensee
resorted to spreading the yellowcake over a 38 ft trough and using propane
heaters placed above and below the trough to dry the material. The material
was dried in batches, and at various intervals workers raked the material to
enhance the drying process. Afterwards, the yellowcake was shoveled back into
the barrels.
During this work the area was washed down on several occasions
to reduce airborne concentrations and surface contamination.
The wash water
was routed to a process sump.
Air sample results ranged as high as 40 times the Derived Air Concentration
for natural uranium specified in 10 CFR 20, Appendix B. However, use of
safety measures, such as respiratory protection and protective clothing, resulted in no detectable levels of uranium in worker urine bioassay samples.
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RETURN TO REGULATORY CENTRAL FILES
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IN 95-54
December 6, 1995 Discussion
Licenses issued to uranium recovery facilities do not specifically prohibit
the kind of activity described above.
However, NRC would expect that
appropriate management oversight and planning would eliminate any need for
such activities. Since production facilities and equipment are designed to
reduce direct exposure to yellowcake by mill workers, special tasks that
bypass these engineered controls should normally be avoided but, if required, be planned with special care to reduce worker exposure.
NRC requires that production facilities and equipment be designed: 1) to
reduce or eliminate worker contact with yellowcake during product drying and
packaging; and 2) to reduce emissions of dried yellowcake to prevent exposures
to workers as well as members of the public. In particular, dryer enclosures
are required and are designed to be maintained at a negative pressure relative
to other mill areas in order to reduce yellowcake outleakage. Also, filtering
components reduce yellowcake emissions from dryer stacks. These design
requirements assume that direct contact with dried yellowcake by workers will
occur only rarely and then only with relatively small quantities.
Uranium processing licensees occasionally may be required to handle
yellowcake. Sampling may disclose that a product batch does not meet customer
specifications and must be re-introduced manually into the process circuit.
On occasion, yellowcake must be transferred from one drum to another.
Such
manual maneuvers have a high potential for airborne contamination and worker
exposure.
Licensees are advised to take measures to minimize the need for special
handling of yellowcake product outside of the processing circuit. When such
work is required, these tasks should be carefully planned to reduce the
potential for airborne contamination and worker exposure.
Each licensee is responsible for protecting the public health and safety by
ensuring that all NRC requirements are met and that any potential hazards are
promptly identified, corrected, and, if necessary, reported. This
responsibility can only be fulfilled if there is persistent and adequate
management oversight of licensed activities.
4
IN 95-54 December 6, 1995 This information notice requires no specific action or written response. If
you have questions about the information in this notice, please contact the
technical contact listed below.
Original Signed By
John T. Greeves, Director
Division of Waste Management
Officer of Nuclear Material Safety
and Safeguards
Technical contact: Chuck Cain, RIV
(817) 860-8186 Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
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MFederline
DOCUMENT NAME:
95-55.IN
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OFFICIAL RECORD COPY
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_i tachment 1 IN 95-55
December 6, 1995 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
95-51
95-50
95-44
95-39
95-29
95-28
95-25
94-64, Supp. 1
Recent Incidents Involving
Potential Loss of Control
of Licensed Material
Safety Defect in Gammamed
12i Bronchial Catheter
Clamping Adapters
Ensuring Combatible Use of
Drive Cables Incorporating
Industrial Nuclear Company
Ball-type Male Conectors
Brachytherapy Incidents
Involving Treatment
Planning Errors
Oversight of Design and
and Fabrication Activities
for Metal Components Used
in Spent Fuel Dry Storage
Systems
Emplacement of Support
Pads for Spent Fuel Dry
Storage Installations at
Reactor Sites
Valve Failure during
Patient Treatment with
Gamma Stereotactic
Radiosurgery Unit
Reactivity Insertion Trans- ient and Accident Limits
for High Burnup Fuel
10/27/95
10/30/95
09/26/95
09/19/95
06/07/95
06/05/95
05/11/95
04/06/95
All material and fuel cycle
licensees.
All High Dose Rate
Afterloader (HDR) Licensees.
All Radiography Licensees.
All U.S. Nuclear Regulatory
Commission Medical
Licensees.
All holders of OLs or CPs
for nuclear power reactors.
Independent spent fuel
storage installation
designers and fabricators.
All holders of OLs or CPs
for nuclear power reactors
All U.S. Nuclear Regulatory
Commission Medical
Licensees.
All holders of OLs or CPs
for Nuclear Power Reactors
and all fuel fabrication
licensees.
'-oitachment 2 IN 95-55
December 6, 1995 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
95-54
95-53
95-47, Rev. 1
94-13, Supp. 2
95-13, Supp. 1
91-29, Supp. 3
94-86, Supp. 1
Decay Heat Management
Practices during
Refueling Outages
Failures of Main Steam
Isolation Valves as a
Result of Sticking
Solenoid Pilot Valves
Unexpected Opening of a
Safety/Relief Valve and
Complications Involving
Suppression Pool Cooling
Strainer Blockage
Control and Oversight of
Contractors during Re- fueling Activities and
Clarificaiton of Applica- bility of Section 50.120 of
Title 10 of The Code of
Federal Regulations to
Contractor Personnel
Potential for Data
Collection Equipment to
Affect Protection System
Performance
Deficiencies Identified
during Electrical
Distribution System
Functional Inspections
Legal Actions Against
Thermal Science, Inc.,
Manufacturer of Thermo-Lag
12/01/95
12/01/95
11/30/95
11/28/95
11/22/95
11/22/95
11/15/95
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 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 holders of OLs or CPs
for nuclear power reactors.
OL - Operating License
CP - Construction Permit
|
|---|
|
| list | - Information Notice 1995-01, DOT Safety Advisory: High Pressure Aluminum Seamless and Aluminum Composite Hoop-Wrapped Cylinders (4 January 1995, Topic: Brachytherapy)
- Information Notice 1995-02, Problems With General Electric CR2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems with General Electric CR2940 Contact Blocks in Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-02, Problems With General Electric Cr2940 Contact Blocks In Medium-Voltage Circuit Breakers (17 January 1995)
- Information Notice 1995-03, Loss of Reactor Coolant Inventory and Potential Loss of Emergency Mitigation Functions While in a Shutdown Condition (3 July 2000, Topic: Reactor Vessel Water Level, Water hammer)
- Information Notice 1995-04, Excessive Cooldown and Depressurization of the Reactor Coolant System Following Loss of Offsite Power (11 October 1996, Topic: Safe Shutdown, Shutdown Margin, Probabilistic Risk Assessment, Loss of Offsite Power, Troxler)
- Information Notice 1995-05, Undervoltage Protection Relay Settings Out of Tolerance Due to Test Equipment Harmonics (20 January 1985)
- Information Notice 1995-06, Potential Blockage of Safety-Related Strainers by Material Brought Inside Containment (25 January 1995, Topic: Foreign Material Exclusion)
- Information Notice 1995-07, Radiopharmaceutical Vial Breakage During Preparation (27 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained With Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-08, Inaccurate Data Obtained with Clamp-On Ultrasonic Flow Measurement Instruments (30 January 1995)
- Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design (31 January 1995, Topic: Operability Determination)
- Information Notice 1995-10, Potential for Loss of Automatic Engineered Safety Features Actuation (3 February 1995, Topic: High Energy Line Break)
- Information Notice 1995-11, Failure of Condensate Piping Because of Erosion/Corrosion at Flow-Straightening Device (24 February 1995, Topic: Feedwater Heater)
- Information Notice 1995-12, Potentially Nonconforming Fasteners Supplied by A&G Engineering II, Inc (21 February 1995)
- Information Notice 1995-13, Potential for Data Collection Equipment to Affect Protection System Performance (24 February 1995)
- Information Notice 1995-14, Susceptibility of Containment Sump Recirculation Gate Valves to Pressure Locking (28 February 1995)
- Information Notice 1995-15, Inadequate Logic Testing of Safety-Related Circuits (7 March 1995)
- Information Notice 1995-16, Vibration Caused by Increased Recirculation Flow in a Boiling Water Reactor (9 March 1995)
- Information Notice 1995-17, Reactor Vessel Top Guide and Core Plate Cracking (10 March 1995, Topic: Safe Shutdown, Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-18, Potential Pressure-Locking of Safety-Related Power-Operated Gate Valves (15 March 1995)
- Information Notice 1995-19, Failure of Reactor Trip Breaker to Open Because of Cutoff Switch Material Lodged in the Trip Latch Mechanism (22 March 1995)
- Information Notice 1995-20, Failures in Rosemount Pressure Transmitters Due to Hydrogen Permeation Into Sensor Cell (22 March 1995)
- Information Notice 1995-21, Unexpected Degradation of Lead Storage Batteries (20 April 1995)
- Information Notice 1995-22, Hardened or Contaminated Lubricant Cause Metal-Clad Circuit Breaker Failures (21 April 1995, Topic: Hardened grease)
- Information Notice 1995-23, Control Room Staffing Below Minimum Regulatory Requirements (24 April 1995, Topic: Shift Technical Advisor)
- Information Notice 1995-24, Summary of Licensed Operator Requalification Inspection Program Findings (25 April 1995, Topic: Job Performance Measure, License Renewal)
- Information Notice 1995-25, Valve Failure During Patient Treatment with Gamma Stereotactic Radiosurgery Unit (11 May 1995, Topic: Overdose)
- Information Notice 1995-26, Defect in Safety-Related Pump Parts Due to Inadequate Treatment (31 May 1995, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1995-27, NRC Review of Nuclear Energy Institute, Thermo-Lag 330-1 Combustibility Evaluation Methodology Plant Screening Guide (31 May 1995, Topic: Safe Shutdown, Fire Barrier, Exemption Request, Fire Protection Program)
- Information Notice 1995-28, Emplacement of Support Pads for Spent Fuel Dry Storage Installations at Reactor Sites (5 June 1995, Topic: Safe Shutdown, Tornado Missile, Safe Shutdown Earthquake, Earthquake)
- Information Notice 1995-29, Oversight of Design and Fabrication Activities for Metal Components Used in Spent Fuel Dry Storage Systems (7 June 1995, Topic: Nondestructive Examination)
- Information Notice 1995-30, Susceptibility of Low-Pressure Coolant Injection Valves to Pressure Locking (3 August 1995, Topic: Hydrostatic, Power-Operated Valves, Overspeed)
- Information Notice 1995-31, Motor-Operated Valve Failure Caused by Stem Protector Pipe Interference (9 August 1995, Topic: Overspeed)
- Information Notice 1995-32, Thermo-Lag 330-1 Flame Spread Test Results (10 August 1995, Topic: Fire Barrier, Overspeed)
- Information Notice 1995-33, Switchgear Fire and Partial Loss of Offsite Power at Waterford Generating Station, Unit 3 (23 August 1995, Topic: Loss of Offsite Power, Overspeed)
- Information Notice 1995-34, Air Actuator and Supply Air Regulator Problems in Copes-Vulcan Pressurizer Power-Operated Relief Valves (25 August 1995, Topic: Loss of Offsite Power, Overspeed)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation (28 August 1995, Topic: Loss of Offsite Power, Overspeed)
- Information Notice 1995-36, Potential Problems with Post-Fire Emergency Lighting (29 August 1995, Topic: Safe Shutdown, Emergency Lighting, Loss of Offsite Power, Exemption Request, Overspeed, Manual Operator Action)
- Information Notice 1995-37, Inadequate Offsite Power System Voltages During Design-Basis Events (7 September 1995, Topic: Loss of Offsite Power)
- Information Notice 1995-38, Degradation of Boraflex Neutron Absorber in Spent Fuel Storage Racks (8 September 1995, Topic: Loss of Offsite Power)
- Information Notice 1995-39, Brachytherapy Incidents Involving Treatment Planning Errors (19 September 1995, Topic: Loss of Offsite Power, Brachytherapy, Underdose)
- Information Notice 1995-40, Supplemental Information to GL-95-03, Circumferential Cracking of Steam Generator Tubes (20 September 1995, Topic: Hydrostatic, Nondestructive Examination)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators (22 September 1995, Topic: Loss of Offsite Power)
- Information Notice 1995-42, Commission Decision on Resolution of Generic Issue 23, Reactor Coolant Pump Seal Failure (22 September 1995, Topic: Loss of Offsite Power)
- Information Notice 1995-43, Failure of Bolt-Locking Device on Reactor Coolant Pump Turning Vane (28 September 1995)
- Information Notice 1995-44, Ensuring Compatible Use of Drive Cables Incorporating Industrial Nuclear Company Ball-Type Male Connectors (26 September 1995)
- Information Notice 1995-45, American Power Service Falsification of American Society for Nondestructive Testing Certificates (4 October 1995, Topic: Commercial Grade)
- Information Notice 1995-46, Unplanned, Undetected Release of Radioactivity from the Exhaust Ventilation System of a Boiling Water Reactor (6 October 1995)
- Information Notice 1995-47, Unexpected Opening of a Safety/Relief Valve & Complications Involving Suppression Pool Cooling Strainer Blockage (30 November 1995)
... further results |
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