Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water ReactorML031060481 |
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: |
03/28/1994 |
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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-94-026, NUDOCS 9403220237 |
Download: ML031060481 (8) |
|
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>. |
- :~
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 March 28, 1994 NRC INFORMATION NOTICE 94-26: PERSONNEL HAZARDS AND OTHER PROBLEMS FROM
SMOLDERING FIRE-RETARDANT MATERIAL IN THE
DRYWELL OF A BOILING-WATER REACTOR
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 licensees to the potential for large amounts of thick, acrid
smoke to be produced from smoldering fire-retardant plastic sheeting. 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 December 28, 1993, a fire occurred in the drywell of the Shoreham Nuclear
Power Station (Shoreham). Shoreham, a boiling-water reactor with a Mark II
containment, is currently undergoing decommissioning. The fire was caused by
hot slag that fell from the 137-foot elevation of the drywell where workers
were cutting a biological shield wall stabilizer support with an oxyacetylene
torch. The hot slag dropped through an opening in the biological shield wall
onto paper toweling and a coil of hemp rope at the 102-foot elevation, setting
them on fire. The burning rope subsequently dropped to the 78-foot level and
landed just below a temporary water collection system in the annulus space
between the lower portion of the reactor pressure vessel support pedestal and
the shield wall. The collection system was constructed of rope *and
fire-retardant plastic sheeting (Herculite and Griffolyn) and had been
installed to collect the runoff of potentially radioactive water expected from
cutting the shield wall. The burning rope made the plastic sheeting smolder, giving off a large quantity of thick, acrid smoke. Because of the smoke, it
was difficult for personnel in the area to breathe and to see in which
direction to go to leave the drywell.
Workers in the area saw the smoke and alerted the control room to a suspected
fire. The control room operators activated the plant fire brigade which
entered the drywell wearing self-contained breathing apparatus. However, the
fire brigade was unable to locate the source of the smoke because the dense
9403220237 k G 9P43R-
~ Al
IN 94-26 March 28, 1994
4-- smoke bl-ocke-d their vision. To help local £ecd the fire brigade asked
the control roomto place the reactor bu;; 1 vefntilation system on
standby 1-This action was not effective a -9rigade leader informed
the confolkreoom that the fire brigade col ide'--source of the smoke.
The control-room operators called the loks mr department to help
find and suppress the fire.
~ --
The plant.jfi-rebrigade made sure that all,; iwd been evacuated from
the area and again searched for the sourei pk'e.-The local fire
department entered the drywell to search;I ¢sand found some burnt
paper toweling and charred rope. About Vt ske in the drywell
began to .clear.-apparently because the cop nattial- feeding the fire
had been-consumed. No flames were observe ev'enht. The plant fire
brigade checked the area for ignition soul undnone. The licensee
suspended-work inside the drywell and coni iivesgate. The licensee
determined that the smoke had come from a- tely 5 5-square-meter
[60-sqUiare-foot]-section of the plastic s, V made'up the collection
trough$ii.'.';4 The licensee determined that the fire had; Sion equipment or
affected nuclear safety. However, 11 perk ~rtedto--the first aid
station suffering from smoke inhalation. : fnd the following
weaknesisesin industrial safety practicesi
- Openings-in the biological shield wa 3beep covered to prevent
hot-slag from passing through.
- Fire protection measures were not ad ood or were not
adequately specified in the fire pet
- The fire permit did not clearly assi f t 'to check the area
for combustible materials before cut ,r -'-al support.
- Workers-were not required to look fo l1hn'ges in the work
area,-,-such as the presence of combus vueable locations.
Discussi6n<-4.;cr
The plastic-sheeting materials involved in f-are commonly used at
many nuclear power stations. Although thi IY ire fire-retardant, they are-capable of generating large amoup n involved in or
exposed-to~a-fire condition. The total ai teila1 that was burned or
smoldered.at Shoreham was small; howeverX 11t'-e smoldering plastic
createdsi'gnificant hazards for personnel~ i£51ajnd made it
impossible for the fire brigade to locatet- X t~he smoke. Because of
the sm6ke, personnel in the drywell were'ii e7ij:-which direction to
go to exit-the drywell or to avoid the fig i]f he plant personnel
suffered smokedinhalation.
-~ X.
IN 94-26 March 28, 1994 The Material Safety data Sheets for the Herculite and Griffolyn sheeting state
that those materials produce hydrogen chloride gas when burned and that self- contained breathing apparatus should be worn when attempting to extinguish
fires involving these materials. In addition to the hazard of smoke
inhalation, there is a potential for toxic side-effects from these fires.
Because these and similar plastic materials are routinely used at nuclear
facilities for contamination control, welding flash shields, and other
purposes, it is important to recognize that, if these materials are exposed to
or are involved in a fire, they generate a large quantity of smoke that
creates hazards for plant workers and may adversely affect plant operations or
fire-fighting efforts. These problems are exacerbated in confined spaces or
in areas with limited ventilation.
This information notice requires no specific action or written response. If
you have any questions about this matter, 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: R. L. Nimitz, RI
(215) 337-5267 F. L. Bower III, RI
(215) 337-5328 P. M. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued NRC Information Notices
doA4-, PLJap 4 6.W
J
'- )itachment
IN 94-26 March 28, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-17, Safety Systems Response 03/25/94 All holders of Ols or CPs
Rev. 1 to Loss of Coolant and for nuclear power.
Loss of Offsite Power
94-25 Failure of Containment 03/25/94 All holders of OLs or CPs
Spray Header Valve to for nuclear power reactors.
Open due to Excessive
Pressure from Inertial
Effects of Water
94-24 Inadequate Maintenance 03/24/94 All holders of OLs or CPs
of Uninterruptible Power for nuclear power reactors.
Supplies and Inverters
94-23 Guidance to Hazardous, 03/25/94 All NRC Licensees.
Radioactive and Mixed
Waste Generators on the
Elements of a Waste
Minimization Program
94-22 Fire Endurance and 03/16/94 All holders of OLs or CPs
Ampacity Derating Test for nuclear power reactors.
Results for 3-Hour Fire- Rated Thermo-Lag 330-1 Fire Barriers
94-21 Regulatory Requirements 03/18/94 All fuel cycle and materials
when No Operations are licensees.
being Performed
94-20 Common-Cause Failures 03/17/94 All holders of OLs or CPs
due to Inadequate for nuclear power reactors.
Design Control and
Dedication
94-19 Emergency Diesel 03/16/94 All holders of OLs or CPs
Generator Vulnerability for nuclear power reactors.
to Failure from Cold
Fuel Oil
OL - Operating License
CP = Construction Permit
IN 94-26 March 28, 1994 The Material Safety data Sheets for the Herculite and Griffolyn sheeting state
that those materials produce hydrogen chloride gas when burned and that self- contained breathing apparatus should be worn when attempting to extinguish
fires involving these materials. In addition to the hazard of smoke
inhalation, there is a potential for toxic side-effects from these fires.
Because these and similar plastic materials are routinely used at nuclear
facilities for contamination control, welding flash shields, and other
purposes, it is important to recognize that, if these materials are exposed to
or are involved in a fire, they generate a large quantity of smoke that
creates hazards for plant workers and may adversely affect plant operations or
fire-fighting efforts. These problems are exacerbated in confined spaces or
in areas with limited ventilation.
This information notice requires no specific action or written response. If
you have any questions about this matter, please contact one of the technical
contacts listed below or the appropriate Office of Nuclear Reactor Regulation
(NRR) project manager. Odgl 11gndby
8ran L GWMes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: R. L. Nimitz, RI
(215) 337-5267 F. L. Bower III, RI
(215) 337-5328 P. M. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued NRC Information Notices
OFFICE SPLB:DSSA:NRR SPLB:DSSA:NRR C/SPLB:DSSA:NRR D/DSSA:NRR
NAME PMadden* SKWest* CEMcCracken* MJVirgilio*
DATE _03/01/94 l03/01/94 03/03/94 ]2/07 TECH ED OGCB:DORS:NRR AC/OGCB:DORS:NRRl
RSanders* JLBirmingham* AJKugler* _ _ me
_G_
03/01/94 103/08/94 03/14/94 - 03/_3/94 OFFFICIAL DOCUMENT NAME: 94-26.IN
IN 94-xx
March xx, 1994 This information notice requires no specific action or written response. If
you have any questions about this matter, please contact one of the persons
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: R. L. Nimitz, RI
(215) 337-5267 F. L. Bower III, RI
(215) 337-5328 P. M. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued Information Notices
OFFICE SPLB:DSSA:NRR SPLB:DSSA:NRR C/SPLB:DSSA:NRR D/DSSA:NRR
NAME PMadden* SKWest* CEMcCracken* MJVirgilio*
DATE 103/01/94 03/01/94 103/03/94 103/07/94 TECH ED OGCB:DORS:NRR jAC/OGCB:DORS:NRR D/DORS:NRR I
RSanders* JLBirmingham* AJKugler j i BKGrimeg
03/01/94 _03/08/94 03/1+/94 103/ /94 j
OFFFICIAL DOCUMENT NAME: FIREIN3.JLB
IN 94-xx
March xx, 1994 This information notice requires no specific action or written response. If
you have any questions about this matter, please contact one of the persons
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: R. L. Nimitz, Region I
(215) 337-5267 F. L. Bower III, Region I
(215) 337-5328 P. M. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued Information Notices
OFFICE SPLB:DSSA:NR-z SPLB:DSSA:§RR C/S P . A-NRR P/DSSA:NRR
NAM E PWest CE_ ___ _ ___
_ _ _o
%471 DATE X i/94 03/1 /94 03/13/94 _03_ _/94 TECH ED Region I OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:NRR
RSanders* lRLNimitz JLBirmi4 &l r BKGrimes
03/01/94 03/ /94 03/ 2'/94 4 03/ /94 1 03/ /94 OFFFICIAL DOCUMENT NAME: FIREIN3.JLB
I Fe--- i
IN 94-xx
March xx, 1994 This information notice requires no specific action or written response. If
you have any questions about this matter, please contact one of the persons
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: R. L. Nimitz, Region I
(215) 337-5267 F. L. Bower III, Region I
(215) 337-5328 P. M. Madden, NRR
(301) 504-2854 Attachment:
List of Recently Issued Information Notices
OFFICE Region I SPLB:DSSA:NRR C/SPLB:DSSA:NRR D/DSSA:NRR
NAME PMadden CEMcCracken ACThadani
DATE 03/ /94 03/ /94 03/ /94 03/ /94 g TECH D OGCB:DORS:NRR AC/OGCB:DORS:NRR D/DORS:NRR
RSanders JLBirmingham AJKugler BKGrimes l
03// /94 03/ /94 03/ /94 03/ /94 l
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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)
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