KR-85 Hazards from Decayed FuelML031130307 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, 05000370 |
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Issue date: |
02/01/1990 |
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From: |
Rossi C Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-90-008, NUDOCS 9001260198 |
Download: ML031130307 (7) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, 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, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, 05000370 |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. 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 [[: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 [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:05000370]] </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 [[: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 [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:05000370]] </code>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 February 1. 1990 NRC INFORMATION
NOTICE NO. 90-08: KR-85 HAZARDS FROM DECAYED FUEL
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors and holders of licenses for permanently
shutdown facilities
with fuel on site.
Purpose
- This information
notice alerts addressees
to potential
problems resulting
from*the .accidental
release of Kr-85 from decayed fuel. It is expected that reci pients will review the Information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, sugges-tions co'ntained
in this information
notice do not constitute
NRC 'requirements;
therefore, no specific action or written response is required.Desripionof
Circumstances:
During the licensing
reviews for the Oconee independent
spent fuel storage Installation,, and in the decommissioning
of the La Crosse and Dresden Unit 1 power reactors, the NRC staff analyzed the radiological
hazards associated.with the gases In decayed spent fuel. The age of the nuclear power industry and the lack of a permanent
repository
for spent fuel have resulted in the accumulation
of decayed'spent
fuel.* Decayed spent fuel is manipulated
after long shutdowns
of operating
reactors, during spent fuel pool re-racking, during mo~vement
to alternate
reactor sites or independent
spent fuel storage instal-lations, and during decommissioning.
Analysis of hypothetical
accidents involving
decayed spent fuel has focused attention
on potential
difficulties
that'could
be associated
with the exposure of onsi1te personnel
to an accidental
release of Kr-85. IKr-85 is a noble gas fission product that is present in the gaps between the fuel pellets and the cladding.
It has a 10.76-year
half-life, and, as a result of the considerably
shorter half-lveso
ital l te gaseous fission products (1-129 being the exception, but in low abundance),, Kr-85 becomes Increasingly
the dominant nuclide in the accident source term for gap releases as decay times increase.
After 2 weeks of decay, Kr-85 is a significant
nuclide in the source term, and after 190 days of decay, it is the predominant
gaseous nuclide for a gap release. The unusual decay character- istics of K~r-85 give cause for focusing attention
on the onsite consequences
of a gap release from decayed fuel.,-9001260198
40--
IN 90-08 February 1, 1990 Discussion:
Kr-85 emits beta radiation
with a maximum energy of 0.67 MeY for 99.6 percent of the decays and 0.51 MeV gamma radiation.
for 0.4 percent of the decays. Conse-quently, direkt exposure to this gas would result in a dose to the skin approxi-mately 100 times the whole-body
dose. Analysis of the relative consequences (in terms of radiological
doses) of a cask-drop
accident as a function of decay time of the fuel is illustrated
in Figure 1. In the event of a serious accident involving
decayed spent fuel, protective
actions would be needed for personnel on site, while offsite doses (assuming
an exclusion
area radius of 1 mile from the plant site) would be well below the Environmental
Protection
Agency's Protective
Action Guides. Accordingly, it is important
to be able to properly survey and monitor for Kr-85, and to assess the skin dose to workers who could be exposed to Kr-85 in the event of an accident with decayed spent fuel.Licensees
may wish to reevaluate
whether Emergency
Action Levels specified
in the emergency
plan and procedures
governing
decayed fuel-handling, activities
appropriately
focus on concern for onsite workers and Kr-85 releases in areas'where decayed spent fuel accidents
could occur, for example, the'spent
fuel pool working floor. Furthermore, licensees
may wish to determine
if emergency plans and corresponding
implementing
procedures
address the means for limiting radiological
exposures
of onsite personnel
who are in other areas of the plant.Among other things, moving onsite personnel
away from the plume and shutting off building air intakes downwind from the source may be appropriate.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.Charles E. Ross Di ctor Division'of
Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
Charles S. Hinson, NRR (301) 492-3142 Robert A. Meck, RES (301) 492-3737 Attachments:
1. Figure 1, Dose Consequences
of a Spent Fuel Drop Accident 2. List of Recently Issued NRC Information
Notices
N N..Atitchment
1 IN 90-08 I February 1, 1990 DOSE CONSEQUENCES
OF A SPENT FUEL DROP ACCIDENT-103 102 ArMR SHUTDOWN Figure 1 Attachment
2 in 90-08 February 1, 1990 Page I of I LIST OF RECENTLT ISSUED NRC INFORMATION
NOTICES}stanntina
V
- _Notice No.BJ-23, Supp. 2..I m ..-90-O7*90-06 90-05 -90-04 90-03 90-02 90-01_- --- 89-90 -_89-89 Subject Potential
for Gas Binding.of Ngh-Prussura
Ssfety InJection
Pumps During a Loss-of-Coolant
Accident New information
Rgarding Insulation
Materal1 Performance
and Debris Blockage of PWR Contain.ment Sumps Potential
for Loss of Shutdown Cooling While at Low Reactor Coolant Levels Inter-Systes
Discharge
of Reactor Coolant Cracking of the Upper Shell-to-TransitIon
Malfunction
of Borg-Warner
Bolted Sonnet Check Valves Caused by Failure of the Swing Arm Potential
Degradation
of Secondary
Containsent
Importance
of Proper Response to Self-Identifled
Violations
by Licensees Pressurizr-Safty
l Lift Setpoint Shift.Eient Notificatin
Workshests
Date or Issuance 1/31/90 1/30/90 Issued to All holders of OLs or CPs for PWRs.All holders of OLts or CPs for nuclear power reactors.1/29/90 All holders of OLs or CPs for nuclear power reactors.1/29/90 1/26/90 1/23/90 All holders of OLs or CPs for nuclear power reactors.All holders'of
OLs or CPs for Westinghouse- designed and Coatustion
Engineering-designed
nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.1/22/90 All holders of OLs.or CPa for BWRs.1/12/90 All holders of NRC materials
licenses.12t/28/81 All olbders or OLs or CPs for Prs.12/26/839 All holders of OLs or CPs for nuclear power reactors:'
OL
License CP
Permit UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555'!OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. UOO IPOSTAGE It FEES PAIDI jusNAcj
-11 --1 IN 90-08 February 1, 1990 Discussion:
Kr-85 emits beta radiation
with a maximum energy of 0.67 MeY for 99.6 percent of the decays and 0.51 MeY gamma radiation
for 0.4 percent of the decays. Conse-quently, direct exposure to this gas would result in a dose to the skin approxi-nately 100 times the whole-body
dose. Analysis of the relative consequences (in terms of radiological
doses) of a cask-drop
accident as a function of decay time of the fuel is illustrated
in Figure 1. In the event of a serious accident involving
decayed spent fuel, protective
actions would be needed for personnel on site, while offsite doses (assuming
an exclusion
area radius of 1 mile from the plant site) would be well below the Environmental
Protection
Agency's Protective
Action Guides. Accordingly, it is important
to be able to properly survey and monitor for Kr-85, and to assess the skin dose to workers who could be exposed to Kr-85 in the event of an accident with decayed spent fuel.Licensees
may wish to reevaluate
whether Emergency
Action Levels specified
in the emergency
plan and procedures
governing
decayed fuel-handling
activities
appropriately
focus on concern for onsite workers and Kr-85 releases in areas where decayed spent fuel accidents
could occur, for example, the spent fuel pool working floor. Furthermore, licensees
may wish to determine
if emergency plans and corresponding
implementing
procedures
address the means for limiting radiological
exposures
of onsite personnel
who are in other areas of the plant.Among other things, moving onsite personnel
away from the plume and shutting off building air intakes downwind from the source may be appropriate.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
NRR project manager.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts:
Charles S. Hinson, NRR (301) 492-3142 Robert A. Meck, RES (301) 492-3737 Attachments:
1. Figure 1, Dose Consequences
of a Spent Fuel Drop Accident 2. List of Recently Issued NRC Information
Notices*See Previous Concurrence
RPB:DREP SC:RPB:DREP
SC:RPB:DREP
DREP D:DREP RPB:ARM C/OG :DOEA:NR CSHinson*
JEWigginton*
LJCunningham*
LCohen* FJCongel*
TechEd* CHBerlinger*
01/11/90 01/11/90 01/17/90 01/17/90 01/24/90 01/25/90 01/25/90 D 9/DOCUMENT NAME: INFORMATION
NOTICE MECK
ef r, .-I IN 90-XX January xx, 1990 DISTRIBUTION:
FJCongel I .9 LJCunningham, NRR THEssig, NRR JEWigginton, NRR RAErickson, NRR RJBarrett, NRR RLAnderson, TTC CSHinson, NRR LKCohen, NRR CHBerlinger, NRR CERossi, NRR Central Files RPB R/F*See Previous Concurrence
RPB:DREP CSHInson*01/11/90 SC:RPB:DREP
JEWigginton*
01/11/90 SC:RPB:DREP
LJCunnlnghal*
01/17/90 DREP LCohen*01/17/90 D:DREP FJCongel*01/24/90 RPB:ARM TechEd*01/25/90 C/d@CB:DOEA:NRR
CHBerlinger
O1/jVi90 D/DOEA:NRR
CERossi 01/ /90 DOCUMENT NAME: INFORMATION
NOTICE MECK
- *}. 'IN 90-XX January xx, 1990 No specific action or written response is required by this information
notice.If you have any questions
about this matter, please contact one of the technical contacts listed below or the Regional Administrator
of the appropriate
regional office.Charles E. Rossi, Director Division of Operational
Events Assessment
Office of Nuclear Reactor Regulation
Technical
Contacts: Charles S. Hinson, NRR (301) 492-3142 Robert A. Heck, RES (301) 492-3737 Attachments:
1.2.Figure 1 List of Recently Issued NRC Information
Notices RPB:DREP SC lPJgBREP CSHinsoIMJ
pginton 01/ll /so ° /90 D/DOEA:NRR
CERossi 01/ /90 4 Cu Ingham LCohen 01/7/90 1/%A 190 D:DRE 2 PB:Mf FJConge T ol1zq/90 01&5/90 onr C/OGCB:DOEA:NRR
CHBerlinger
01/ /90
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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, 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)
- 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, 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)
- 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, 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: Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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