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 ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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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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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 not
problems. However, suggestions contained in this information notice are
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 to
reached 82 *C [180 OF]. The licensee began a controlled power reduction
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.and At
this time, the upper bearing temperature reached nearly 93 *C [200 OF],
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 fire
removed insulation and extinguished the fire using portable dry chemical
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' 7i* -I1c -
TXK
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 Debris in Containment 08/12/94 All holders of OLs or CPs
and the Residual Heat for nuclear power reactors.
Removal System
94-56 Inaccuracy of Safety Valve 08/11/94 All holders of OLs or CPs
Set Pressure Determinations for nuclear power reactors.
Using Assist Devices
94-55 Problems with Copes- 08/04/94 All holders of OLs or CPs
Vulcan Pressurizer for nuclear power reactors.
Power-Operated Relief
Valves
91-79, Deficiencies Found in 08/04/94 All holders of OLs or CPs
Supp. 1 Thermo-Lag Fire Barrier for nuclear power reactors.
Installation
94-54 Failures of General 08/01/94 All holders of OLs or CPs
Electric Magne-Blast for nuclear power reactors.
Circuit Breakers to
Latch Closed
91-45, Possible Malfunction of 07/29/94 All holders of OLs or CPs
Supp. 1 Westinghouse ARD, BFD, for nuclear power reactors.
and NBFD Relays, and
A200 DC and DPC 250
Magnetic Contactors
94-42, Cracking in the Lower 07/19/94 All holders of OLs or CPs
Supp. 1 Region of the Core Shroud for boiling water reactors
in Boiling-Water Reactors (BWRs).
94-53 Hydrogen Gas Burn Inside 07/18/94 All holders of OLs or CPs
Pressurizer During Welding for nuclear power reactors.
94-52 Inadvertent Containment 07/15/94 All holders of OLs or CPs
Spray and Reactor Vessel for nuclear power reactors.
Draindown at Millstone
Unit 1 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-
- SPLB:DSSA *DRS:RI *OGCB:DORS *TECH ED
EAConnell RJPaolino PCWen JMain
07/21/94 07/21/94 07/21/94 07/21/94
- SC/DSP:RI *SC/SPLB:DSSA *C/SPLB:DSSA *AD/DSSA
WHRuland SKWest CEMcCRACKEN MJVirgil io
07/21/94 07/21/94 07/2Z19402/ 07/25/94
- C/OEAB:DORS *AC/OGCB:DORS
AEChaffee ElDoolittle
07/26/94 07/28/94 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
- SPLB:DSSA *DRS:RI *OGCB: DORS *TECH ED
EAConnell RJPaolano PCWen JMain
07/21/94 07/21/94 07/21/94 07/21/94
- SC/DSP:RI *SC/SPLB:DSSA *C/SPLB:DSSA *AD/DSSA
WHRuland SKWest CEMcCRACKEN MJVirgilio
07/21/94 07/21/94 07/22/94 07/25/94
- C/OEAB:DORS *AC/OGCB:DORS D/DORS
AEChaffee ELDoolittle BKGrimes9fL
07/26/94 07/28/94 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
- SPLB:DSSA *DRS:RI *OGCB:DORS *TECH ED
EAConnell RJPaolino PCWen JMain
07/21/94 07/21/94 07/21/94 07/21/94
- SC/DSP:RI *SC/SPLB:DSSA *C/SPLB:DSSA *AD/DSSA
WHRuland SKWest CEMcCRACKEN MJVirgilio
07/21/94 07/21/94 07/22/94 07/25/94
AEChaffee E le BKGrimes
07/26/94 07/ /94
1,0-w
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. Si ubsequently, 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.
~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
- SPLB:DSSA *DRS:RI *OGCB:DORS *TECH ED
EAConnell RJPaolino PCWen JMain
07/21/94 07/21/94 07/21/94
- SC/DSP:RI *SC/SPLB:DSSA " P DSA AD/DSSAOA '
WHRuland SKWest CEMcCRACKEN MJVirqilio
07/21/94 07/21/94 07/Ap94 s 07/$6/94 C lG ORS AC/OGCB:DORS D/DORS
A0a ffee ELDoolittle BKGrimes
07/A/94 07/ /94 07/ /94 OFFICIAL RECORD COPY 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 J. Paolino,RI
(610) 337-5285 Attachment:
List of Recently Issued NRC Information Notices
SPLB:DSSA DRS:RI OGCB:gQRS TECH ED
EAConnell RJPaol ino PCWen 1- JMain asp
07/Z/ /94 07 I/94 07,l1/94 07/21/94 SC/DSP: R C/SPLB:DSSA AD/DSSA
WHRul and SKWest CEMcCRACKEN MJVirgilio
-8 07/%1/94 07/t- /94 07/ /94 07/ /94 C/OEAB:DORS AC/OGCB:DORS D/DORS
AEChaffee ELDoolittle BKGrimes
07/ /94 07/ /94 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)
- 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)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994)
- 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)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy)
- 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)
- 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)
- 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)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier)
- 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 1994-35, 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)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: 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)
- 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)
... further results |
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