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, 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, 05000000, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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, 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, 05000000, 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 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 [[: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 [[:05000000]] 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 [[:05000000]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </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 isexpected 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 inthe 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 ismanipulated 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 isa noble gas fission product that is present inthe
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 inthe accident source term
for gap releases as decay times increase. After 2 weeks of decay, Kr-85 is
a significant nuclide inthe 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
V _*
Attachment 2 in90-08 February 1, 1990
Page I of I
LIST OF RECENTLT ISSUED
NRCINFORMATION NOTICES
}stanntina
Date or
Notice No. Subject Issuance Issued to
BJ-23, Potential for Gas Binding 1/31/90
Supp. 2 All holders of OLs
.of Ngh-Prussura Ssfety or CPs for PWRs.
InJection Pumps During a
Loss-of-Coolant Accident
. . I m . . -
90-O7* New information Rgarding 1/30/90 All holders of OLts
Insulation Materal1 or CPs for nuclear
Performance and Debris power reactors.
Blockage of PWR Contain.
ment Sumps
90-06 Potential for Loss of 1/29/90 All holders of OLs
Shutdown Cooling While or CPs for nuclear
atLow Reactor Coolant power reactors.
Levels
90-05 - Inter-Systes Discharge of 1/29/90 All holders of OLs
Reactor Coolant or CPs for nuclear
power reactors.
90-04 Cracking of the Upper Shell- 1/26/90 All holders'of OLs
to-TransitIon Cone 6irth or CPs for Westinghouse- Welds in Steam Generators designed and Coatustion
Engineering-designed
nuclear power reactors.
90-03 Malfunction of Borg-Warner 1/23/90 All holders of OLs
Bolted Sonnet Check Valves or CPs for nuclear
Caused by Failure of the power reactors.
Swing Arm
90-02 Potential Degradation of 1/22/90
Secondary Containsent All holders of OLs.
or CPa for BWRs.
90-01 Importance of Proper 1/12/90 All holders of NRC
Response to Self-Identifled materials licenses.
Violations by Licensees
_- --- 89-90 -_ Pressurizr-Safty l
Lift Setpoint Shift. 12t/28/81 All olbders or OLs
or CPs for Prs.
89-89 Eient Notificatin 12/26/839 All holders of OLs
Workshests or CPs for nuclear
power reactors:'
OL
CP
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555'! IPOSTAGE ItFEES
jusNAcj
PAIDI
OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. UOO
- 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
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:
FJCongelI . 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
RPB:DREP SC:RPB:DREP SC:RPB:DREP DREP D:DREP RPB:ARM C/d@CB:DOEA:NRR
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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. Figure 1
2. List of Recently Issued NRC Information Notices
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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, 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: Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
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