Hydrogen Gas Burn Inside Pressurizer During WeldingML031060575 |
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: |
07/18/1994 |
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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-94-053, NUDOCS 9407080212 |
Download: ML031060575 (22) |
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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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 July 18, 1994 NRC INFORMATION NOTICE 94-53: HYDROGEN GAS BURN INSIDE PRESSURIZER DURING
WELDING
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
ui
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to the potential for the ignition of hydrogen gas
mixtures during welding operations while the reactor coolant system is
depressurized. 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 February 3, 1994, a control room operator at Surry Power Station, Unit 1, observed pressure spikes on the pressurizer level instruments. At the same
time, a loud rumbling sound was heard in the containment. The containment
vent radiation alarm was received, and as a precaution, the containment was
evacuated.
At the time of the event, the pressurizer was drained and vented to both the
pressurizer relief tank and the containment atmosphere through a filtered
covering over the piping where the safety valves had been removed. The
reactor vessel head had just been detensioned. There was fuel in the reactor
vessel. A modification to eliminate the pressurizer loop seals was in
progress.
The pressure fluctuations inside the pressurizer caused the expulsion of
radioactive gases from the pressurizer into the containment causing alarms on
both the containment radiation monitor and the ventilation radiation monitor
where the ongoing filtered containment purge was directed. Licensee personnel
calculated the release rate through the monitored ventilation purge path to be
approximately 30 percent of the technical specification limits. One worker
received an estimated internal exposure of 70 pSv [7 mrems] and a total dose
of 160 pSv [16 mrems].
The licensee investigation showed that the screens for excluding foreign
material that were taped over the pressurizer side of the piping where the
94070q0212 PDR -fiE Aq{CN 53071
"M~eAOzv4 i A ia
fit
. I i i
IN 94-53 July 18, 1994 three safety valves were removed were discolored and appeared burned. The
licensee concluded that a hydrogen gas burn had occurred inside the
pressurizer. Welding activities associated with the pressurizer loop seal
modification had ignited the hydrogen gas that had come out of solution and
accumulated inside the pressurizer and associated piping. There were no
personnel inquiries.
Additional details pertaining to this event can be found in Licensee Event
Report 50-280/94-001 dated March 4, 1994, and NRC Inspection Report
50-280/94-002 dated March 7, 1994.
Discussion
During refueling operations, the reactor coolant system was depressurized and
the pressurizer level was drained while a nitrogen blanket was provided via
the pressurizer relief tank. Before the coolant system was depressurized, the
system was degassed and the hydrogen concentration was reduced to less than
5 cc/kg in accordance with recommendations from Westinghouse, the nuclear
steam system supplier.
The source of the hydrogen gas inside the pressurizer was investigated by the
licensee's root cause team. The team concluded that pockets of trapped gas
either in the reactor coolant system or in the pressurizer relief tank had
moved as a result of the effects of changing containment pressure on the
pressurizer. The pressure changes had acted through the removed safety valve
openings. Because the licensee had maintained the containment at a slight
negative pressure during most of the refueling shutdown, opening and closing
of the equipment hatch caused changes in the containment pressure.
The licensee investigation showed that a similar event had occurred at the
Wolf Creek Nuclear Plant in October 1987.
The licensee imposed additional controls for welding on the primary system.
These require that samples be taken and analyzed before initiating an arc to
determine if explosive gasses are present. The licensee also evaluated
pressurizer stresses associated with the rapid hydrogen burn and completed a
piping support inspection and internal inspection of the pressurizer. The
evaluation showed that no unacceptable stresses had resulted, and no damage
was noted during the inspections.
Related Generic Communications
In Information Notice 82-28, 'Hydrogen Explosion While Grinding in the
Vicinity of Drained and Open Reactor Coolant System," the NRC described a
hydrogen gas explosion that took place when maintenance personnel at Arkansas
Nuclear One, Unit 1, were grinding a recently cut high-pressure injection
pipe. The cut was approximately 46 centimeters [18 inches] from the nozzle
connecting the injection pipe to the reactor coolant system piping.
. I
KY IN 94-53 July 18, 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 manaIger. /7 rian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Morris Branch, RII
(804) 357-2101 Mark A. Caruso, NRR
(301) 504-3235 Attachment:
List of Recently Issued NRC Information Notices
r
4J c (6Sc'Aht ri6z1 r,&. J4,
. I I
A'Attachment
IN 94-53 July 18, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
94-51 Inappropriate Greasing 07/15/94 All holders of OLs or CPs
of Double Shielded Motor for nuclear power reactors.
Bearings
94-50 Failure of General 07/14/94 All holders of OLs or CPs
Electric Contactors for nuclear power reactors.
to Pull in at the
Required Voltage
94-49 Failure of Torque 07/06/94 All holders of OLs or CPs
Switch Roll Pins for nuclear power reactors.
94-48 Snubber Lubricant 06/30/94 All holders of OLs or CPs
Degradation in High- for nuclear power reactors.
Temperature Environments
94-13, Unanticipated and Unin- 06/28/94 All holders of OLs or CPs
Supp. 1 tended Movement of Fuel for nuclear power reactors.
Assemblies and other
Components due to Improper
Operation of Refueling
Equipment
94-47 Accuracy of Information 06/21/94 All U.S. Nuclear Regulatory
Provided to NRC during Commission Material
the Licensing Process Licensees.
94-46 NonConservative Reactor 06/20/94 All holders of OLs or CPs
Coolant System Leakage for nuclear power reactors.
Calculation
94-45 Potential Common-Mode 06/17/94 All holders of OLs or CPs
Failure Mechanism for for nuclear power reactors.
Large Vertical Pumps
OL = Operating License
CP = Construction Permit
IN 94-53 July 18, 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.
Odfgtnl gned by
Sdan K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Morris Branch, RII
(804) 357-2101 Mark A. Caruso, NRR
(301) 504-3235 Attachment:
List of Recently Issued NRC Information Notices
- see JRJohnson memorandum to BKGrimes dated April 4, 1994 and Drevious concurrence sheets
OFFICE *RPB2/REG-II *C:RPB2/REG-I1 *DRP/REG-II *D:DRS/REG-II
NAME GABelisle MVSinkule JPJaudon AFGibson
DATE 3/21/94 3/22/94 3 _2994_3/3 1/94 OFFICE *D:DRP/REG-II *OGCB/NRR *Tech Editor *SRXB/NRR
NAME JRJohnson RJKiessel MMejac MACaruso
DATE 4/ 4/94 5/5/94 5/9/94 5/16/94 OFFICE *C:SRXB/NRR *D:DSSA/NRR *AC:OGCB\NRR D l
NAME TECollins MJVirgilio RLDennig Gr es l
DATE 5/18/94 6/11/94 6/15/94 7/e /94 Document Name: 94-53.IN
IN 94-xx
June 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: Morris Branch, Region II
(804) 357-2101 Mark A. Caruso, NRR
(301) 504-3235 Attachment:
List of Recently Issued NRC Information Notices
- see JRJohnson memorandum to BKGrimes dated April 4, 1994 and previous concurrence sheets
OFFICE *RPB2/REG-II *C:RPB2/REG-II *DRP/REG-II *D:DRS/REG-41 NAME GABelisle MYSinkule JPJaudon AFGibson
DATE 3/21/94 3/22/94 3/29/94 3/31/94 OFFICE *D:DRP/REG-II *OGCB/NRR *Tech Editor *SRXB/NRR
NAME JRJohnson RJKiessel MMeJac MACaruso
DATE 4/ 4/94 5/5/94 5/9/94 5/16/9M
OFFICE *C:SRXB/NRR *D:DSSA/NRR *AC:OGCB\NRR D:DORS/NRR
NAME TECollins MJVirgilio RLDennig BKGrimes
DATE 5/18/94 6/11/94 6/15/94 6/ /84 Document Name: NRCIN.451
IN 94-xx
May 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: Morris Branch, Region II
(804) 357-2101 Mark A. Caruso, NRR
(301) 504-3235 Attachment:
List of Recently Issued NRC Information Notices
- see JRJohnson memorandum to BKGrimes dated April 4, 1994
-
and Previous concurrence sheets
OFFICE *RPB2/REG-II *C:RPB2/REG-II *DRP/REG-II *D:DRS/REG-I1 NAME GABelisle MVSinkule JPJaudon AFGibson
DATE 3/21/94 3/22/94 3/29/94 3/31/94 OFFICE *D:DRP/REG-II *OGCB/NRR *Tech Editor SRXB/NRR
NAME JRJohnson RJKiessel MMejac MACaruso J
DATE 4/ 4/94 5/5/ 9/94 5//b/94 OFFICE C:SRXB/NRR D:DSSA/NR P B/NRR C. ,RPB/NR <
NAME TECollin~4lr
RiJVirgilio JDB n LCu am
DATE 5/g/941 (X14/ a L9u /9Jh
OFFICE 'bsPRSS/NRR,--' D:DORS/NRR 11 NAME FJC[y 6X/e Y
BKGrimes 7 DATE XI /94 \"N &4 1fl/94 5/ /84 I.)
Document Name: NRCIN.451
t
Attachments:
1. List of Recently Issued NRC Information Notices
- see JRJohnson memorandum to BKGrimes dated April 4, 1994 and previous concurrence sheets
OFFICE *RPB2/REG-II *C:RPB2/REG-II *DRP/REG-II *D:DRS/REG-II
NAME GABelisle MVSinkule JPJaudon AFGibson
DATE 3/21/94 3/22/93 3/29/94 3/31/94 OFFICE *D:DRP/REG-II OGCB/NRR Tech Editor SRXB/NRR
NAME JRJohnson RJKiessel& 2 !e;_ MACaruso
DATE 4/ 4/94 5/ "/94 5/q /94 5/ /94 OFFICE C:SRXB/NRR D:DSSA/NRR PRPB/NRR C:PRPB/NRR
NAME TECollins MJVirgilio JDBuchanan LCunningham
DATE 5/ /94 5/ /94 5/ /94 5/ /94 OFFICE D:DRSS/NRR C:OGCB\NRR D:DORS/NRR
NAME FJCongel AJKugler BKGrimes
DATE 5/ /94 5/ /94 5/ /84 Document Name: G:\RJK\NRCINS\NRCIN.451
r . 05-.OZE-1994 14:27 841 S510 US NRC RG II P.03 K>
Brian K. Grimes 21 APR - 4 1994 cc w/encl cont'd:
M. Branch, RI
G. Lainas, NRR
H. Berkow, NRR
B. Buckley, NRR
R. Benedict, NRR
I
RII:DRP RP f R S
RI 4RP RI JDV
GB Isle MSinkul e JJaud n AG s on
03/s /94 03 4 V/,294 O3 94 03A31/94 I
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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 1994-42, 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)
- Information Notice 1994-47, Accuracy of Information Provided to NRC During the Licensing Process (21 June 1994)
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