Recent Orifice Plant ProblemsML031130240 |
Person / Time |
---|
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
10/05/1990 |
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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-90-065, NUDOCS 9009280166 |
Download: ML031130240 (10) |
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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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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[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 [[: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 October 5, 1990
NRC INFORMATION NOTICE NO. 90-65: RECENT ORIFICE PLATE PROBLEMS
Addressees
nuclear power
All holders of operating licenses or construction permits for
reactors.
Purpose
This information notice is intended to alert addressees to that recent problems that
recipients will
have been identified with orifice plates. It is expected and consider
review the information for applicability to their facilities suggestions
actions, as appropriate, to avoid similar problems. However, contained in this information notice do not constitute NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances
associated
Recent licensee and NRC inspections have identified two problems in the reverse
with orifice plates. Namely, the installation of orifice plates
direction and the deformation of orifices in the direction of flow.
operators at
With respect to the first of the two problems, on August 8, 1988, error in
the San Onofre Nuclear Generating Station, Unit 1, discovered-an revealed
several daily calorimetric power calibrations. Further investigation
indication
that one of the three feedwater flow indicators was providing flow in the
that was lower than the actual feedwater flow. This error resulted as much as
indicated power on the nuclear instrumentation system being adjusted determined
four percent lower than the actual reactor power. The licensee
backwards, that the orifice plate for the deficient flow indicator was installed evaluation
causing the indicated flow to be less than the actual flow. Subsequent
showed that all accident scenarios described in the Final Safety Analysis
Unit
Report produced acceptable results despite the error. In 1985, San Onofre
1 reported a similar event (LER 50-206/85-014).
Nuclear
During an NRC walkdown of the containment spray system at the Farley element
Plant in April 1989, inspectors found that an orifice plate in a flow
spray additive tank
had been installed backwards. The flow element provided
found four
flow indication in the control room. The licensee subsequently feedwater
other orifice plates, used in the charging system, the auxiliarySimilarly, in
system, and the containment spray system, that were reversed.
July 1989 the Shearon Harris Nuclear Power Plant found a reversed orifice
the
plate. This orifice plate also was used to determine the flow rate for
containment spray system spray additive tank.
(< O 92 8 1 66 v 7C
IN 90-65 October 5, 1990 Reversed orifice plates have also been found at the Salem Nuclear Generat- ing Station, Brunswick Steam Electric Plant, Waterford Steam Electric Plant, Surry Power Station, and North Anna Power Station. At the Salem plant, in
May 1989, the flow metering orifices for the high-head cold leg safety injection
line were found installed backwards. After the orifices were correctly
installed, the indicated flow rate was 15 percent greater. At Brunswick, in
February 1989, the licensee discovered a flow restricting orifice installed
backwards in the high-pressure core injection minimum flow line, and in two
other systems. Waterford experienced problems with low indicated flow in the
recirculation line of a high pressure safety injection pump. The problem was
traced to a reversed flow orifice in May 1989. At Surry in August 1989, an NRC
inspector discovered a reversed flow orifice after the completion of a corrective
action program aimed at flow orifices. Further walkdowns by the licensee
identified two additional flow orifices installed backwards. At North Anna in
September 1989, a total of nine flow orifices were determined to be installed
backwards. Only orifices which are accessible during power operation were
inspected. The root cause of these events has generally been determined to be
inadequate procedures for and inspection of installations.
In February 1989, a second problem with orifice plates was identified at
Brunswick, i.e., several flow restricting orifices were deformed in the direc- tion of flow. The orifices were located in the residual heat removal system, the core spray injection and minimum flow line, and the high-pressure coolant
injection system. Each of the orifice plates was manufactured from A240-316
- statless-steel-arnd-was 8-inch-thik- _ltisth-icknes-Swas based on standard
orifice design that did not consider the thickness needed to prevent deforma- tion caused by flow and the differential pressure across the orifice plate.
In one instance, the orifice bore had increased from 1.021 inches to 1.088 inches, and the plate had ballooned outward approximately 0.5 inch. Subse- quently, the licensee evaluated the design of the orifice plates using allow- able material stresses, orifice plate geometric configurations, and system flow
rates. The results of this evaluation indicated that the applied stress
exceeded several times the allowable material yield stress. The licensee
determined that the root cause of the deformation was an inadequate design
thickness specification.
Discussion:
An orifice plate is commonly used as a primary flow element, and produces a
differential pressure from which a flow rate can be determined., Orifice plates
have a handle on which pertinent data is permanently marked, such as orifice
diameter, flange size, pressure rating, and, as appropriate, the word "In- let." The two most common types of orifice plates are squared edge and beveled
edge. On a beveled edge orifice plate that is properly installed, the word
Inlet" faces the inlet direction and the beveled edge faces the outlet direc- tion. A square edged orifice plate is not dependent upon orientation to
perform its function. However, Installation procedures for both types of
orifice plates should be consistent. A beveled orifice plate that is installed
backwards would provide a lower differential pressure across the flow element, resulting in a flow rate measurement that is lower than the actual flow rate.
IN 90-65 October 5, 1990 Orifice plates are also used as flow restrictors, to provide a specific
hydraulic resistance in a piping system to limit flow rate. A failure of
the orifice plate could cause excessive recirculation or bypass flow, which may
decrease the flow being delivered to the main flow path during an accident.
The failure of the orifice plate could also reduce the hydraulic resistance in
the system, increasing the total pump flow rate and the probability of centrif- ugal pump runout. Runout could damage the internal components of the pump, lead to inadequate net positive suction head, and overload the pump motor.
Increased flow rates in the orificed line could also lead to increased pipe
vibration and erosion. In addition, permanently deformed orifice plates could
provide inaccurate flow measurements.
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.
A Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Scott Sparks, Region II
(404) 331-4187 Andrew Kugler, NRR
(301) 492-0834 Attachment: List of Recently Issued NRC Information Notices
I
Attachment 1 IN 90-51 October 5, 1990
Page I of I
LIST OFRECENTLY ISSUED
NRCINFORMATION NOTICES
Intormation cat. or
Notice no. SubJect Issuance Issued to
90-64 Potential for Comma-Mode 10/4/90 All holders of
Failure of High Pressure OLs or CPs for
Safaty Injectlon Pumps or pressurized-water
Release of Reactor Coolant reactors.
Outside Containment During
A Loss-Of-Coolant Accident
90-43 Management Attention to the 10/3/90 All fuel cycle
Establishment and Main. licensees possess- tenance of A Nuclear Ing more than
Criticality Safety Program crtrcal mss
quantities of
special nuclear
material.
90-42 Requirements for Import 9/25/90 All irradiated
and Distribution of gemstone importers
Neutron-Irradiated Goes end distributors.
and all non-power
licensees.
90-41 Potential for Residual 9/20/90 All holders of
Heat Removal Pump OLs or CPs for
Pump Damage Caused By nuclear power
Parallel Pump interaction reactors.
90-60 Availability of Failure 9/20/90 All holders of
Data In the Government. OLs or CPs for
Industry Data Exchange nuclear power
Program reactors.
90-59 Errors In the Use of 9/17/90 All medical
Radioactive todine-131 licensees.
90-58 Improper Handling of 9/11/90 All NRCmedical
- Opttaft&Strontiua.9L . _ iceasees.
Beta Radiation Applicators
90-S7 Substandard, Refurbished 9/5/90 All holders of OLs
Potter S Brumfield Relays or CPs for nuclear
Misrepresented As Nw power reactors.
OL
CP* Construction Permit
UNITED STATES FIRST CLAS MAIL
NUCLEAR REGULATORY COMMISSION POSTAGE & FEES PAID
WASHINGTON, D.C. 2055 USNAC:
PERMIT@ No a9 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE. $300
IN 90-65 October 5, 1990 Orifice plates are also used as flow restrictors, to provide a specific
hydraulic resistance in a piping system to limit flow rate. A failure of
the orifice plate could cause excessive recirculation or bypass flow, which may
decrease the flow being delivered to the main flow path during an accident.
The failure of the orifice plate could also reduce the hydraulic resistance in
the system, increasing the total pump flow rate and the probability of centrif- ugal pump runout. Runout could damage the internal components of the pump, lead to inadequate net positive suction head, and overload the pump motor.
Increased flow rates in the orificed line could also lead to increased pipe
vibration and erosion. In addition, permanently deformed orifice plates could
provide inaccurate flow measurements.
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.
, n-Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: Scott Sparks, Region II
(404) 331-4187 Andrew Kugler, NRR
(301) 492-0834 Attachment: List of Recently Issued NRC Information Notices
Document Name: ORIFICE
- SEE PREVIOUS CONCURRENCES
- SEE PREVIOUS FAX CONCURRENCE
- OGCB:DOEA:NRR **RII *RPB:ADM C/OGCB:DOEA:NRR D/DOEALI _-
AJKugler SSparks TechEd CHBerlinger CERossir
09/06/90 09/10/90 09/12/90 09/26/90 W/, /90
IN 90-XX
September xx, 1990 Orifice plates are also used as flow restrictions, which provide a specific
hydraulic resistance in a piping system to limit the flow rate. A failure of
the orifice plate could cause excessive recirculation or bypass flow, which may
decrease the flow being delivered to the main flow path during an accident.
The failure of the orifice plate could also reduce the hydraulic resistance in
the system, increasing the total pump flow rate and the probability of centrif- ugal pump runout. Runout could damage the internal components of the pump, lead to inadequate net positive suction head, and overload the pump motor.
Increased flow rates in the orificed line could also lead to increased pipe
vibration and erosion. In addition, permanently deformed orifice plates could
provide inaccurate flow measurements.
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: Scott Sparks, Region II
(404) 331-4187 Andrew Kugler, NRR
(301) 492-0834 Attachment: List of Recently Issued NRC Information Notices
Document Name: ORIFICE
- SEE PREVIOUS CONCURRENCES
- SEE PREVIOUS FAX CONCURRENCE
- OGCB:DOEA:NRR **RII *RPB:ADM CB:DOEA:NRR D/DOEA:NR?,,
AJKugler SSparks TechEd CHBerlinger CERoss I
09/06/90 09/10/90 09/12/90 094 /90 09/ /90
IN 90-XX
September xx, 1990 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: Scott Sparks, Region II
(404) 331-4187 Andrew Kugler, NRR
(301) 492-0834 Attachment: List of Recently Issued NRC Information Notices
Document Name: ORIF
OGCB:DOEANRR RII # RPB:ADM C/OGCB:DOEA:NRR D/DOEA:NRR
AKugler 4t SSparks TechEd ,* CHBerlinger CERossi
09/06/90 09/ /90 09/ /90 09/ /90 09/ /90
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09/06/90
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IN 90-XX
September xx, 1990
I 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: Scott Sparks, Region II
(404) 331-4187 Andrew Kugler, NRR
(301) 492-0834 Attachment: List of Recently Issued NRC Information Notices
Document Name: ORIF
OGCB:DOEA:NRR RII RPB:ADM C/OGCB:DOEA:NRR D/DOEA:NRR
AKugler SSparks TechEd MYWr- CHBerlinger CERossi
09/ /90 09/ /90 09/]i/0 09/ /90 09/ /90
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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: Siren)
- Information Notice 1990-43, Mechanical Interference with Thermal Trip Function in GE Molded-Case Circuit Breakers (29 June 1990)
... further results |
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