Reactor Coolant Pump Lube Oil FireML031060498 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
08/16/1994 |
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From: |
Grimes B Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-94-058, NUDOCS 9408100058 |
Download: ML031060498 (9) |
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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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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 [[: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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
lQ UNITED STATES C, NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 August 16, 1994 NRC INFORMATION
NOTICE 94-58: REACTOR COOLANT PUMP LUBE OIL FIRE
Addressees
All holders of operating
licenses or construction
permits for pressurized- water reactors.Purnose The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to a problem that may exist with the oil collection
system for the lube oil system components
of reactor coolant pumps. 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 NRC requirements;
therefore, no specific action or written response is required.DescriDtion
of Circumstances
Haddam Neck Plant On July 11, 1994, while operating
at 100 percent power, the licensee for the Haddam Neck Plant received a low oil level alarm for the upper lube oil reservoir
of reactor coolant pump No. 3. The licensee later observed that the upper bearing temperature
for reactor coolant pump No. 3 had been increasing
for approximately
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> prior to receiving
the low oil level alarm and reached 82 *C [180 OF]. The licensee began a controlled
power reduction
to bring the plant to a power level condition
which would allow the reactor coolant pump to be taken out of service. Simultaneously, a maintenance
crew was entering containment
to fill the oil reservoir.
Upon entering containment, the maintenance
crew observed smoke Just inside the airlock. At this time, the upper bearing temperature
reached nearly 93 *C [200 OF], and the licensee manually tripped the reactor from approximately
50 percent power.The heat detectors
installed
above the reactor coolant pump went into alarm approximately
50 minutes later. At about the same time, the fire brigade entered containment
and reported a fire in the insulation
around the pump casing and nearby piping of reactor coolant pump No. 3. The fire brigade removed insulation
and extinguished
the fire using portable dry chemical fire extinguishers.
A relief crew later observed a reflash on the remaining insulation, removed this insulation, and extinguished
the second fire.The licensee determined
that the oil leak and subsequent
fire resulted from a crack in a 1-inch diameter, schedule 80, threaded PVC fitting in the pump lube oil system. The PVC fitting was installed
between the reactor coolant pump 9408100058 P' JTT-i-E f'I' TXK 7i* -I1c -
v @ j 4-58 Yugust 16, 1994 oil reservoir
and the oil lift pump to electrically
isolate the oil lift pump from the reactor coolant pump motor. The oil leaking from the crack was not properly collected
and routed away from high velocity cooling air, which blew the oil onto the insulation
on the pump casing and pipe. The cooling air came from the reactor coolant pump motor and the area ventilation
system. The high temperature
of the reactor coolant system (approximately
282 C [540 *F])ignited the oil-soaked
insulation. (The flash point of the lube oil is approximately
204 'C [400 'F].) The reservoir
retained about 455 liters[120 gallons] of the approximately
755 liters (200 gallons] of oil originally
in the reservoir.
About about 150 liters (40 gallons] of oil was collected
by the oil collection
system, and 150 liters [40 gallons] leaked onto the insulation
and the containment
floor.Millstone
Nuclear Power Station. Unit 2 On July 27, 1994, the lube oil low flow alarm for the 'A' reactor coolant pump annunciated
at Millstone
Unit 2. Plant operators
began reducing reactor power in accordance
with plant procedures.
Licensee personnel
inspected
all of the reactor coolant pumps and found that oil had dripped from the tops of the 'A'and 'D' pump motors, coating the outside of the motors. Most of the oil was contained
by the oil collection
drip pans; however, some of the oil that leaked from the 'A' pump motor was not contained.
Based on the observed fire hazard in containment, the licensee shut down the plant.After the plant was shut down, an NRC inspector
examined the lube oil collection
system and the area around the reactor coolant pumps. There were a number of small oil leaks on each pump motor although there was more leakage from the 'A' pump motor. The inspector
observed that various equipment
around the 'A' reactor coolant pump was coated with a film of oil and he estimated that several gallons of oil had collected
in various areas outside the oil collection
system. The inspector
also noted that portions of the lube oil system were outside the oil collection
system and that the collection
system piping did not appear to be large enough to accommodate
the largest potential oil leak.Discussion
In pressurized-water
reactors, each reactor coolant pump motor typically contains between 530 and 830 liters [140 and 220 gallons) of oil. Oil leaking from the lube oil system may come in contact with either (1) surfaces that are hot enough to ignite the oil, or (2) an electrical
source of ignition.Appendix R to Part 50 of Title 10 of the Code of Federal Regulations
requires the installation
of an oil collection
system to collect oil from all potential pressurized
and unpressurized
leakage sites. An adequately
designed, installed, and maintained
oil collection
system is necessary
to contain any oil released because of leakage or failure of the lubrication
system and to minimize fire hazards by draining the oil to a safe location.There are a number of differences
between the reactor coolant pump motors and their associated
lube oil systems at Millstone
Unit 2 and Haddam Neck. For example, the Millstone
Unit 2 motors do not use PVC or other synthetic couplings
in the lube oil system. The Millstone
Unit 2 reactor coolant pump
V <\,AN 94-58 August 16, 1994 motors are manufactured
by General Electric Company while the motors at Haddam Neck are manufactured
by Westinghouse
Electric Corporation.
However, the oil collection
systems at the two plants are similar.The Haddam Neck oil collection
system is intended to collect lube oil from all potential
leakage sites and to drain it to a vented, closed container
to prevent a fire during normal conditions
or design basis accident conditions.
However, in this event the catch pan design, which relied on an unshielded
vertical flow of oil, was not adequate.
This design allowed the air flow around the motor to affect the vertical movement of the dripping oil and allowed it to escape the collection
system. To a lesser extent, the ventilation
system also created air currents in the vicinity of the pump, which prevented
some of the oil from being collected.
The licensee is installing
a steel dielectric
union on each reactor coolant pump motor at Haddam Neck to replace the PVC fitting which failed and caused the leak in this event. The licensee is also modifying
the oil collection
system to account for air currents near the reactor coolant pumps.The ventilation
system for the Millstone
Unit 2 containment
does not contribute
to the air flow around the reactor coolant pump motors. The only air flow in this area is caused by the motor itself. In addition, Millstone Unit 2 has installed
mirror insulation
on some of the piping in the vicinity of the reactor coolant pumps. This type of insulation
would prevent oil from coming in contact with and igniting on the high temperature
piping it insulates.
These factors reduce, but do not eliminate, the likelihood
of leaking lube oil reaching an ignition source. However, the design of the existing oil collection
system was inadequate
to contain existing and potential
oil leakage paths. The licensee is evaluating
modifications
that can be installed
during the current forced outage to ensure that the lube oil collection
system for the reactor coolant pump motors meets the requirements
of Appendix R.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
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Edward A. Connell, NRR (301) 504-2838 Ralph J. Paolino, RI (610) 337-5285 Attachment:
List of Recently Issued NRC Information
Notices
Att&,.Aent
IN 94-58 August 16, 1994 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 94-57 94-56 94-55 91-79, Supp. 1 Debris in Containment
and the Residual Heat Removal System Inaccuracy
of Safety Valve Set Pressure Determinations
Using Assist Devices Problems with Copes-Vulcan Pressurizer
Power-Operated
Relief Valves Deficiencies
Found in Thermo-Lag
Fire Barrier Installation
Failures of General Electric Magne-Blast
Circuit Breakers to Latch Closed Possible Malfunction
of Westinghouse
ARD, BFD, and NBFD Relays, and A200 DC and DPC 250 Magnetic Contactors
08/12/94 08/11/94 08/04/94 08/04/94 08/01/94 07/29/94 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.94-54 91-45, Supp. 1 94-42, Supp. 1 Cracking in the Lower Region of the Core Shroud in Boiling-Water
Reactors 07/19/94 All holders for boiling (BWRs).of OLs or CPs water reactors 94-53 94-52 Hydrogen Gas Burn Inside Pressurizer
During Welding Inadvertent
Containment
Spray and Reactor Vessel Draindown
at Millstone Unit 1 07/18/94 07/15/94 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
IJN 94-58 August 16, 1994 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
Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Brian K. Grimes Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Edward A. Connell, NRR (301) 504-2838 Ralph J. Paolino, RI (610) 337-5285 Attachment:
List of Recently Issued NRC Information
Notices rnL'- P -fiicAI-*See previous*SPLB:DSSA
EAConnell 07/21/94 concurrence
- DRS:RI RJPaolino 07/21/94*OGCB:DORS
PCWen 07/21/94*TECH ED JMain 07/21/94*SC/DSP:RI
WHRuland 07/21/94*C/OEAB:DORS
AEChaffee 07/26/94*SC/SPLB:DSSA
SKWest 07/21/94*AC/OGCB:DORS
ElDoolittle
07/28/94*C/SPLB:DSSA
CEMcCRACKEN
07/2Z19402/
- AD/DSSA MJVirgil io 07/25/94 08//o/94 OFFICIAL RECORD COPY DOCUMENT NAME: 94-58. IN NOTES:* The PM was informed of the development
of this Infor. Notice.* The licensee was consulted
with the technical
content of this Infor. Notice, and its comments were incorporated.
Subsequently, the final version was shown to R. Paolino (RI) and P. Madden (SPLB).They have no further comments.* This version also addressed
OEAB's comments.
\_J IN 94-xx August xx, 1994 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
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts:
Edward A. Connell, NRR (301) 504-2838 Ralph J. Paolino, RI (610) 337-5285 Attachment:
List of Recently Issued NRC Information
Notices*See previous*SPLB:DSSA
EAConnell 07/21/94 concurrence
- DRS:RI RJPaolano 07/21/94*OGCB: DORS PCWen 07/21/94*TECH ED JMain 07/21/94*SC/DSP:RI
WHRuland 07/21/94*SC/SPLB:DSSA
SKWest 07/21/94*C/SPLB:DSSA
CEMcCRACKEN
07/22/94*AD/DSSA MJVirgilio
07/25/94*C/OEAB:DORS
AEChaffee 07/26/94*AC/OGCB:DORS
ELDoolittle
07/28/94 D/DORS BKGrimes9fL
08/ /94 v OFFICIAL RECORD COPY DOCUMENT NAME: HADMNECK.IN
NOTES:* The PM was informed of the development
of this Infor. Notice.* The licensee was consulted
with the technical
content of this Infor. Notice, and its comments were incorporated.
Subsequently, the final version was shown to R. Paolino (RI) and P. Madden (SPLB).They have no further comments.* This version also addressed
OEAB's comments.
'->IN 94-xx July xx, 1994 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
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Edward A. Connell, NRR (301) 504-2838 Ralph J. Paolino,RI
(610) 337-5285 Attachment:
List of Recently Issued NRC Information
Notices*See previous*SPLB:DSSA
EAConnell 07/21/94 concurrence
- DRS:RI RJPaolino 07/21/94*OGCB:DORS
PCWen 07/21/94*TECH ED JMain 07/21/94*SC/DSP:RI
WHRuland 07/21/94*SC/SPLB:DSSA
SKWest 07/21/94 AC RS E le*C/SPLB:DSSA
CEMcCRACKEN
07/22/94*AD/DSSA MJVirgilio
07/25/94*C/OEAB:DORS
AEChaffee 07/26/94 D/DORS BKGrimes 07/ /94 1,0-w OFFICIAL RECORD COPY DOCUMENT NAME: HADMNECK.IN
NOTES:* The PM was informed of the development
of this Infor.* The licensee was consulted
with the technical
content Infor. Notice, and its comments were incorporated.
Si the final version was shown to R. Paolino (RI) and P.They have no further comments.* This version also addressed
OEAB's comments.Notice.of this ubsequently, Madden (SPLB)~t. 7A/94
'JIN 94-xx July xx, 1994 The licensee is considering
flanged connections
to replace the PVC fittings.The licensee is also modifying
the oil collection
system to account for the air currents near the RCPs.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
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Edward A. Connell, NRR (301) 504-2838 Ralph J. Paolino,RI
(610) 337-5285 Attachment:
List of Recently Issued NRC Information
Notices*See previous concurrence
RJPaolino 07/21/94 07/21/94*SC/DSP:RI
WHRuland SKWest 07/21/94 07/21/94 C G l ORS AC/OGCB:DORS
A0a ffee ELDoolittle
07/A/94 07/ /94 OFFICIAL RECORD COPY*OGCB:DORS
PCWen" P DSA CEMcCRACKEN
07/Ap94 s D/DORS BKGrimes 07/ /94*TECH ED JMain 07/21/94 AD/DSSAOA
'MJVirqilio
07/$6/94 DOCUMENT NAME: HADNECK.RI
V',-AN 94-xx July xx, 1994 The licensee is considefing
flanged connections
to replace the PVC fittings.The licensee is also modifying
the oil collection
system to account for the air currents near the RCPs.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
Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
Reactor Support Office of Nuclear Reactor Regulation
Technical
contacts: Edward A. Connell, NRR (301) 504-2838 Ralph (610)J. Paolino,RI
337-5285 Attachment:
List of Recently Issued NRC Information
Notices SPLB:DSSA EAConnell 07/Z/ /94 SC/DSP: R WHRul and-8 07/%1/94 C/OEAB:DORS
AEChaffee 07/ /94 DRS:RI RJPaol ino 07 I/94 SKWest 07/t- /94 AC/OGCB:DORS
ELDoolittle
07/ /94 OGCB:gQRS PCWen 1-07,l1/94 C/SPLB:DSSA
CEMcCRACKEN
07/ /94 TECH ED JMain asp 07/21/94 AD/DSSA MJVirgilio
07/ /94 D/DORS BKGrimes 07/ /94 OFFICIAL RECORD COPY DOCUMENT NAME: HADNECK.RI
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994, Topic: Overspeed trip, Overspeed)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994, Topic: Overspeed)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994, Topic: Overspeed)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994, Topic: Overspeed)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy, Overspeed)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy, Overspeed)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier, Water hammer)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier, Operability Determination)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier, Local Leak Rate Testing)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic, Stress corrosion cracking)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Stress corrosion cracking, Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier, Stress corrosion cracking)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994, Topic: Unidentified leakage)
... further results |
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