Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose NozzlesML070180065 |
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, 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: |
04/14/1994 |
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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-94-031, NUDOCS 9404080170 |
Download: ML070180065 (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, 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 [[: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 [[: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 April 14, 1994 NRC INFORMATION NOTICE 94-31: POTENTIAL FAILURE OF WILCO, LEXAN-TYPE HN-4-L
FIRE HOSE NOZZLES
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert the addressees of the potential for failure of Lexan- type HN-4-L fire hose nozzles. 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.
Description of Circumstances
On August 3, 1992, the licensee for the H.B. Robinson facility experienced a
failure of a 1 1/2-inch Lexan-type HN-4-L fire hose nozzle during a routine
fire hose hydrostatic pressure test. Following the failure, the licensee
revised their procedures to require the use of a ball-style shutoff nozzle
during future pressurization tests. On June 17, 1993, the licensee
experienced another failure of a Lexan-type HN-4-L nozzle during a regularly
scheduled fire hose station flush. The nozzle failed when it was pressurized
to nominal firemain pressure. Following this event, the licensee replaced
Lexan-type HN-4-L nozzles with ball-style shutoff nozzles.
Discussion
During a fire hose pressurization test on August 3, 1992, the Lexan- type HN-4-L nozzle attached to a hose being tested was shut to pressurize the
hose to the final test pressure of 1,756 kPa [254.7 psia]. With the hose
pressurized to approximately 1,204 kPa [174.7 psia], the nozzle failed.
Following a review of the event, the licensee revised their fire hose
hydrostatic test procedure to require the use of ball-style shutoff nozzles.
On June 17, 1993, a similar failure of a Lexan-type HN-4-L nozzle occurred
during a routine flush of an installed fire hose station. With the nozzle
shut and the fire hose charged to the nominal system pressure of 1,032 kPa Y r
[149.7 psia], the nozzle failed.
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IN 94-31 April 14, 1994 The nozzles were both 1 1/2-inch diameter, Lexan (polycarbonate) fog nozzles.
Originally, Wilco (Wilson and Cousins Company) manufactured these nozzles, which are now manufactured by the A. Burks Pump Company. They are designated
as Model HN-4-L and are approved by Factory Mutual Insurance Company for fire
hose station use. The testing performed by Factory Mutual included a
hydrostatic test at 6,895 Kpa (1000 psi) and an operational test at pressures
up to 2,069 Kpa (300 psi).
Though the licensee does not track the installation of fire nozzles, it is
estimated that both nozzles had probably been in service for several years.
The nozzles consist of a stationary inner casing attached to the fire hose
fitting. An outer shell is threaded onto this inner casing. The outer shell
is twisted to adjust or start/stop flow. In both of the failures, the inner
casing separated at the third land for the inner casing-outer shell thread.
No indications of imminent failure were present in either failure. An
examination of the threaded area on some disassembled nozzles did not reveal
indications of cracking.
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.
CQL~
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: C. Ogle, RII
(803) 383-4571 W. Orders, RII
(803) 383-4571 P. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued NRC Information Notices
At.dchment
IN 94-31 April 14, 1994 Page I of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
90-68, Stress Corrosion Cracking 04/14/94 All holders of 01 or CPs
Supp. 1 of Reactor Coolant Pump for pressurized water
Bolts reactors.
94-30 Leaking Shutdown Cooling 04/12/94 All holders of OLs or CPs
Isolation Valves at for nuclear power reactors.
Cooper Nuclear Station
94-29 Charging Pump Trip during 04/11/94 All holders of OLs or CPs
a Loss-of-Coolant Event for pressurized water
Caused by Low Suction reactors.
Pressure
92-51, Misapplication and 04/12/94 All holders of OLs or CPs
Supp. I Inadequate Testing of for nuclear power reactors.
Molded-Case Circuit
Breakers
94-28 Potential Problems with 04/05/94 All holders of OLs or CPs
Fire-Barrier Penetration for nuclear power reactors.
Seals
94-27 Facility Operating 03/31/94 All holders of OLs or CPs
Concerns Resulting from for nuclear power reactors.
Local Area Flooding
94-26 Personnel Hazards and 03/28/94 All holders of OLs or CPs
Other Problems from for nuclear power reactors.
Smoldering Fire-Retard- ant Material in the
Drywell of a Boiling- Water Reactor
93-17, Safety Systems Response 03/25/94 All holders of OLs or CPs
Rev. I to Loss of Coolant and for nuclear power.
Loss of Offsite Power
OL = Operating-License
CP = Construction Permit
IN 94-31 April 14, 1994 The nozzles were both 1 1/2-inch diameter, Lexan (polycarbonate) fog nozzles.
Originally, Wilco (Wilson and Cousins Company) manufactured these nozzles, which are now manufactured by the A. Burks Pump Company. They are designated
as Model HN-4-L and are approved by Factory Mutual Insurance Company for fire
hose station use. The testing performed by Factory Mutual included a
hydrostatic test at 6,895 Kpa (1000 psi) and an operational test at pressures
up to 2,069 Kpa (300 psi).
Though the licensee does not track the installation of fire nozzles, it is
estimated that both nozzles had probably been in service for several years.
The nozzles consist of a stationary inner casing attached to the fire hose
fitting. An outer shell is threaded onto this inner casing. The outer shell
is twisted to adjust or start/stop flow. In both of the failures, the inner
casing separated at the third land for the inner casing-outer shell thread.
No indications of imminent failure were present in either failure. An
examination of the threaded area on some disassembled nozzles did not reveal
indications of cracking.
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.
orig /s/'d by CIGrimes/for
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: C. Ogle, RII
(803) 383-4571 W. Orders, RII
(803) 383-4571 P. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrences
SPLB:DSSA* SPLB:DSSA* SPLB:DSSA* DSSA:NRR* OGCB:DORS*
PMadden SWest CMcCracken AThadani TJKim
10/15/93 10/15/93 ,10/15/93 10/15/93 10/28/93 Tech Ed* OGCB:DORS* DORS:NRR
DGables AKugler BKGrimee -s/
10/25/93 03/17/94 04/ /94 -,
DOCUMENT NAME: 94-31.iN
IN 94-XX
March XX, 1994 The nozzles were both I 1/2-inch diameter, Lexan (polycarbonate) fog nozzles.
Originally, Wilco (Wilson and Cousins Company) manufactured these nozzles, which are now manufactured by the A. Burks Pump Company. They are designated
as Model HN-4-L and are approved by Factory Mutual Insurance Company for fire
hose station use. The testing performed by Factory Mutual included a
hydrostatic test at 6,895 Kpa (1000 psi) and an operational test at pressures
up to 2,069 Kpa (300 psi).
Though the licensee does not track the installation of fire nozzles, it is
estimated that both nozzles had probably been in service for several years.
The nozzles consist of a stationary inner casing attached to the fire hose
fitting. An outer shell is threaded onto this inner casing. The outer shell
is twisted to adjust or start/stop flow. In both of the failures, the inner
casing separated at the third land for the inner casing-outer shell thread.
No indications of imminent failure were present in either failure. An
examination of the threaded area on some disassembled nozzles did not reveal
indications of cracking.
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: C. Ogle, RII
(803) 383-4571 W. Orders, RII
(803) 383-4571 P. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrences
SPLB:DSSA* SPLB:DSSA* SPLB:DSSA* DSSA:NRR* OGCB:DORS*
PMadden SWest CMcCracken AThadani TJKim
10/15/93 10/15/93 10/15/93 10/15/93 10/28/93 Tech Ed*. OGCB:DORS* DORS:NRR
DGables AKugler BKGrimes
10/25/93 03/17/94 03/ /94 ,
DOCUMENT NAME: 93-113.IN
IN 94-XX
March XX, 1994 The nozzles were both I 1/2-inch diameter, Lexan (polycarbonate) fog nozzles.
Originally, Wilco (Wilson and Cousins Company) manufactured these nozzles, which are now manufactured by the A. Burks Pump Company.. They are designated
as Model HN-4-L and are approved by Factory Mutual Insurance Company for fire
hose station use. Though the licensee does not track the installation of fire
nozzles, it is estimated that both nozzles had probably been in service for
several years. The nozzles consist of a stationary inner casing attached to
the fire hose fitting. An outer shell is threaded onto this inner casing.
The outer shell is twisted to adjust or start/stop flow. In both of the
failures, the inner casing separated at the third land for the inner casing- outer shell thread. No indications of imminent failure were present in either
failure.. An examination of the threaded area on some disassembled nozzles did
not reveal indications of cracking.
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: C. Ogle, RII
(803) 383-4571 W. Orders, RII
(803) 383-4571 P. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued NRC Information Notices
- See previous concurrences
SPLB:DSSA* SPLB:DSSA* SPLB:DSSA* DSSA:NRR* OGCB:DORS*
PMadden SWest CMcCracken AThadani TJKim
10/15/93 10/15/93 10/15/93 10/15/93 10/28/93 Tech Ed* OGCB:DORS DORS:NRR
DGables AKugler6k BKGrimesi'A
10/25/93 03/17/94 03/ /941C
DOCUMENT NAME: 93-113.IN
IN 93-XX
October XX, 1993 The nozzles were both 1 1/2-inch diameter, Lexan (polycarbonate) fog nozzles.
They were originally produced by Wilco (Wilson and Cousins Company), but are
now manufactured by Prosser Industries. They are designated as Model HN-4-L
and were approved by Factory Mutual Insurance Company for fire hose station
use. Though the licensee does not track the installation of fire nozzles, it
is estaimated that both nozzles had probably been in service for several
years. The nozzles consist of a stationary inner casing attached to the fire
hose fitting. Onto this inner casing, an outer shell is threaded. The outer
shell is twisted to adjust or start/stop flow. In both of the failures, the
inner casing separated at the third land for the inner casing-outer shell
thread. No indications of imminent failure were present in either failure.
An examination of the threaded area on some disassembled nozzles did not
reveal indications of cracking.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contacts listed below or the appropriate NRR project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: C. Ogle, RII
(803) 383-4571 W. Orders, RII
(803) 383-4571 P. Madden, NRR
(301) 504-2854 At t.hment: List Recently Issued NRC Information Notices
4-'I_.IDSSA --. S4'1SM:DSSA SPLB:DSSA DSSAAiR OGCAR-S
PMadden SWest CMcCra.cken AThadani TJKim
10/),e;/93 101//,-,/93 10//')/93 10//1 93 10/28/93 OGCB:DORS DORS:NRR
D. G-W6k s GHMarcus BKGrimes
10/7-5/93 10/ /93 10/ /93 DOCUMENT NAME: 93-113.IN
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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)
- 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 trip)
- 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, Topic: Stress corrosion cracking)
- 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, 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: 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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