Facility Operating Concerns Resulting from Local Area FloodingML031060478 |
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: |
03/31/1994 |
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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-94-027, NUDOCS 9403250222 |
Download: ML031060478 (9) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 March 31, 1994 NRC INFORMATION NOTICE 94-27: FACILITY OPERATING CONCERNS RESULTING FROM
LOCAL AREA FLOODING
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 addressees to emergency preparedness, equipment operability
and radiological control problems that may result from local area flooding.
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.
Background
The Cooper Nuclear Station is located between Nemaha and Brownville, Nebraska
and is adjacent to the Missouri River. The facility floor and plant grade
elevations are about 275 meters [903 feet] above mean sea level. The
elevation of the area surrounding the plant is about 271.3. meters [890 feet]
and the area is protected by a levee to an elevation of 274.9 meters
[902 feet]. The normal groundwater table is 267.9 meters [879 feet]. The
level for the 1000-year flood and the 10,000-year flood are predicted to be
274.3 and 274.9 meters (900 and 902 feet], respectively. During this event, the Missouri River peaked at 274.6 meters (900.8 feet].
Description of Circumstances
During the months of June and July 1993, the State of Nebraska and several
surrounding states experienced record rainfalls that caused flooding over
extensive areas. In accordance with plant flood procedures, the licensee for
the Cooper Nuclear Station had placed barriers around the entrances to the
reactor building, the radwaste building, the turbine building and the diesel
generator rooms when the water level in the Missouri River reached 273.4 meters [897 feet]. On July 21, the licensee began a reactor startup from a
scheduled refueling and maintenance outage. At that time, the river level was
273.1 meters [896 feet] and decreasing.
On July 22 and 23, the river level rose rapidly and, at 10:35 a.m. on July 23, the licensee decided to shut down the reactor. At 6:19 p.m. on July 23, the
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IN 94-27 March 31, 1994 licensee declared a Notice Of Unusual Event when the water level in the
Missouri River reached 274.0 meters [899 feet]. The river level continued to
rise and subsequently peaked at 274.6 meters [900.8 feet]. The elevated river
level caused the closure of several area roads including a portion of
Interstate 29 and Route 136 in the State of Missouri which isolated one of the
planned emergency evacuation routes.
Subsequent to the reactor shutdown, the licensee noted increased inleakage.
The vital area rooms outside of the radiologically controlled areas were
relatively dry with only a minor amount of water leaking in through the
concrete walls below ground elevation. However, some of the below-grade rooms
inside radiologically controlled areas in the turbine building and the reactor
building, had extensive inleakage. In some cases, the inleakage significantly
challenged the capacity of the floor drains. Examples of this problem were:
(1) a lower hallway in the turbine building where standing water was found and
water was leaking in around safety-related cable trays and (2) the
turbine-driven feedwater pump rooms where water was dripping on control boxes, and the floor drain system had backed up so that standing water from within
areas known to be radiologically contaminated had migrated out into designated
clean areas. The NRC inspectors observed that plant personnel had not taken
actions to identify the areas where inleakage was occurring and had not
established measures to divert the water away from important components. The
turbine building inleakage was eventually stopped when the licensee pumped out
the underground cable tunnels that encircled the plant. The heavy rains had
flooded the cable tunnels and water was covering the manways and storm drains
at grade level.
Similar problems were observed in the reactor building quadrant rooms and
torus room. Water leaking into the reactor core isolation cooling (RCIC) pump
room was impinging on RCIC electrical components: Subsequently, an
annunciator lit up indicating a ground in the RCIC 250-V dc circuitry. This
ground was apparently caused by water that had entered into some of the RCIC
circuitry. The water leaking into the torus room was impinging on junction
boxes and other electrical components. The inleakage in these areas was not
appreciably reduced when the licensee pumped out the cable tunnels and storm
drains. However, the inleakage did decrease as the river level dropped.
Discussion
This event demonstrates that flooding problems and degradation of equipment
may be caused by water inleakage even though flood waters are not above grade
elevations. Water leaking through underground walls may impinge on electrical
equipment or may enter radiologically controlled areas and spread
contamination to other areas. Underground cable and pipe tunnels may become
flooded and serve as pathways for water to enter plant buildings. Management
and plant personnel attention to these conditions is important to ensure that
equipment is protected and unsafe facility conditions are not created. The
IN 94-27 March 31, 1994 NRC previously discussed problems caused by water leakage through conduit
seals into plant buildings in NRC Information Notice 92-69, "Water Leakage
From Yard Area Through Conduits Into Buildings."
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, irector
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: W. B. Jones, RIV
(817) 860-8147 J. L. Birmingham, NRR
(301) 504-2829 Attachment:
List of Recently Issued NRC Information Notices
I
Attachment
IN 94-27 March 31, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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. 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
OL = Operating License
CP - Construction Permit
\1--/ v
IN 94-27 March 31, 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 ignld W
Brian K. GrimeS
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: W. B. Jones, RIV
(817) 860-8147 J. L. Birmingham, NRR
(301) 504-2829 Attachment:
List of Recently Issued NRC Information Notices
OFFICE l C/ECGB:DE:NRR l D:DE:NRR
NAME Ghoutam Bagchi* WHodges*
DATE 03/16/94 1 03/16/94 OFFICE REGION IV REGION IV EAB:DORS:NRR C/OEAB:DORS:NRR
NAME WBJones* TWesterman* NHunemuller* AChaffee*
DATE 02/23/94 02/23/94 02/23/94 02/24/94 OFFICE TECHED:RPB OGCB:DORS:NRR C/OGCB:DORS:NRR D
NAME RSanders* JBirmingham* AJKugler* ,Z
DATE 02/16/94 02/24/94 03/04/94 03i/Z7/94 Commenis from the Emergency Preparedness Branch have been included, they
indicated that they did not need to be on concurrence.
OFFICIAL DOCUMENT NAME: 94-27.IN
IN 94-xx
March 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: W. B. Jones, RIV
(817) 860-8147 J. L. Birmingham, NRR
(301) 504-2829 Attachment:
List of Recently Issued NRC Information Notices
OFFICE C/ECGB:DE:NRR D:DE:NRR
NAME Ghoutam Bagchi* WHodges*
DATE 03/16/94 03/16/94 OFFICE REGION IV REGION IV EAB:DORS:NRR C/OEAB:DORS:NRR
NAME WBJones* TWesterman* NHunemuller* AChaffee*
DATE [02/23/94 102/23/94 02/23/94 102/24/94 OFFICE TECHED:RPB OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR
NAME RSanders* JBirmingham* AJKugler* BKGrimes
DATE 1 02/16/94 I 02/24/94 1 03/04/94 103/ /94
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Comments Trom Mne Emergency Preparedness Brancn nave Dieen included, thiey
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indicated that they did not need to be on concurrence.
OFFICIAL DOCUMENT NAME: CNSFLOOD.JLB
. I JK-I
J-1 IN 94-xx
March xx, 1994 This information notice requires ino specific action or written response. If
you have any questions about the l Information in this notice, please contact
one of the people 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 contact: W. B. Jones, R-IV
(817) 860-8147 J. L. Birmingham, NRR
(301) 504-2829 Attachment:
List of Recently Issued NRC Information Notices
-013 -to
I OFFICE E:NRR D R
DATE Bagchi N od es
lDATE to~4
03ENS l03/ty/94 OFFICE REGION-IV REGION-IV EAB:DORS:NRR C/OEAB:DORS:NRR
NAME WBJones* TWesternman* NHunemuller* AChaffee*
DATE 102/23/94 ,02/23/94 ,02/23/94 ,02/24/94 OFFICE TECHED:RPB OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR
NAME RSanders* JBirmingham* AJKugler* BKGrimes
DATE 02/16/94 J02/24/94 103/04/94 03/ /94 OFFICIAL DOCUMENT NAME: CNSFLOOD.JLU
- I
IN 94-xx
March 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 people 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 contact: W. B. Jones, Region IV
(817) 860-8147 J. L. Birmingham, NRR
(301) 504-2829 Attachment:
List of Recently Issued NRC Information Notices
lOFFICE REGION-IV REGION-IV EAB:DORS:NRR C/OEAB:DORS:NRR
NAME WBJones* TWesterman* NHunemuller* AChaffee*
DATE 02/23/94 02/23/94 102/23/94 02/24/94 OFFICE TECHED:RPB OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR l
NAME RSanders* JBirmingham* AJKulerk BKGRIMES
DATE 02/16/94 02/24/94 O3/D+/94 03/ /94 n'r-6 Comments were received anu IncUrpUrLteU I rum URe t::IIWI pJQI
1-J PI cullcaa Mu all'-Il
but they asked not to be on concurrence.
OFFICIAL DOCUMENT NAME: CNSFLOOD.JLB
IN 94-xx
March 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
the person 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 contact: W. B. Jones, Region IV
(817) 860-8147 Attachment:
List of Recently Issued NRC Information Notices
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NAME WBJos TWestermra6 lNHunemuller AChaffee t
DATE 02/23/94 1 02/23/94 1 02/23/94 02/j 94 OFFICE TECHED:RPB OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR
NAME RSanders* JBirmingham GHMarcus BKGRIMES
DATE , 02/16/94 nrr~~t.--
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1 02/ /94 102/ /94 UOFlFAL LWUUMINI NAML: LNSFLUUU.JLb
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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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