Snubber Lubricant Degradation in High-Temperature EnvironmentsML031060631 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/30/1994 |
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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-94-048, NUDOCS 9406240045 |
Download: ML031060631 (20) |
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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 June 30, 1994 NRC INFORMATION NOTICE 94-48: SNUBBER LUBRICANT DEGRADATION
IN HIGH-TEMPERATURE ENVIRONMENTS
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 the possible degradation of the lubricant used
in mechanical snubbers manufactured by Pacific Scientific (PSA) when the
snubber is used in a high-temperature environment. 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.
DescriDtion of Circumstances
During the ninth refueling outage at the Joseph M. Farley Nuclear Plant, Unit 2 at the end of 1993, the Southern Nuclear Operating Company (the
licensee) functionally tested a number of safety-related snubbers as
prescribed by its technical specification surveillance requirements. From an
original test sample of 88 mechanical snubbers, the licensee identified
8 failures. Two of these failures, a PSA-1/4 on a steam generator blowdown
line and a PSA-10 on a pressurizer safety valve, led to the discovery of four
additional snubbers that failed their functional tests for common causes
(three more PSA-1/4s on steam generator blowdown lines and another PSA-10 on
the pressurizer).
The licensee concluded that high environmental temperatures (ranging from 38 to 93 *C [100 to 220 'F]) for extended periods had degraded the internal
lubricants used in these PSA snubbers. The licensee determined that the
failure mechanism of the PSA-1/4s was a loss of lubricant, and for the PSA-10s
it was a breakdown of lubricant viscosity. Elevated temperatures caused the
PSA-1/4 snubber grease to bake and dry up, resulting in complete lockup when
these snubbers were tested. For the PSA-10 snubbers, the high temperatures
caused the grease to lose almost all viscosity,iresulting in insufficient drag
resistance during testing.
9406240045
2 ad~ 6 /3°o/Cqty
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'~ IN 94-48 June 30, 1994 The licensee subsequently replaced all failed snubbers, and conducted physical
inspections and engineering evaluations to ascertain if any structural damage
had occurred. No support damage or system operability concerns were
identified by the licensee.
Discussion
The licensee does not have the capability to overhaul mechanical snubbers.
Consequently, unlike their hydraulic counterparts, mechanical snubbers are not
part of any routine preventive maintenance program. PSA mechanical snubbers
are purchased and installed with the expectation that they are maintenance
free for the duration of their life in the plant. The physical conditions of
all snubbers are examined by visual inspections which, depending on the number
of unacceptable snubbers identified in the previous inspection interval, could
be performed once in every 36 months. Although the operability of some
snubbers is verified by functional testing each refueling outage, only a small
sample of the snubber population is exercised and tested. Past industry
experience with snubber failures has demonstrated that the failure modes of
mechanical snubbers are not readily discernible by visual inspection or even
physical str.'ing. Only functional testing under actual load conditions
appears to confirm their operability. For example, of all the functionally
tested mechanical PSA snubber failures identified by the licensee for both
units since commercial operation, only one was discovered by visual
inspection.
Depending on the size and distribution of the snubber population, sample
selection techniques and failure rates, it may take decades before all plant
snubbers are actually tested. In the case of Farley Unit 2, none of the
failed PSA snubbers had been tested since the unit began commercial operation
in 1981. The subject PSA-1/4 and PSA-10 snubbers were installed during
original construction and were about 15 years old.
The licensee concluded that the failure of PSA snubbers as the result of
lubricant degradation after extended exposure to high temperatures is a new
issue. The Snubber Utility Group (SNUG), of which the licensee is a member, and PSA are aware of the issue. In December of 1993, PSA sent letters to all
users of its snubbers, including Farley Unit 2, informing them of these
grease-related problems. Although PSA snubbers are lubricated with a
radiation-resistant grease (i.e., NRRG-159), recent test results from PSA and
the industry also indicate there could be an adverse impact on the service
life of snubbers in environments with elevated temperatures. PSA and the SNUG
Lubrication Working Group have requested users to inspect and evaluate all PSA
snubbers removed from service because of preventive maintenance or functional
failure for possible lubrication degradation. SNUG also requested utilities
to forward any relevant information using a standard data sheet.
~- IN 94-48 June 30, 1994 PSA and SNUG are establishing a database to analyze and develop criteria based
on time and temperature for a service life program to be used by all
utilities. The NRC staff is following the above industry activities and will
evaluate whether additional NRC actions are necessary.
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.
nanK. Grimes, Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Floyd S. Cantrell, RII
(404) 331-5534 Arnold J. H. Lee, NRR
(301) 504-2758 Attachment:
List of Recently Issued NRC Information Notices
Attaachment
IN 94-48 June 30, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
94-44 Main Steam Isolation 06/16/94 All holders of OLs or CPs
Valve Failure to Close for nuclear power reactors.
on Demand because of
Inadequate Maintenance
and Testing
94-43 Determination of Primary- 06/10/94 All holders of OLs or CPs
to-Secondary Steam for pressurized water
Generator Leak Rate reactors.
94-42 Cracking in the Lower 06/07/94 All holders of OLs or CPs
Region of the Core for boiling-water reactors
Shroud in Boiling-Water (BWRs).
Reactors
94-41 Problems with General 06/07/94 All holders of OLs or CPs
Electric Type CR124 for nuclear power reactors.
Overload Relay Ambient
Compensation
OL = Operating License
CP = Construction Permit
IN 94-48 June 30, 1994 PSA and SNUG are establishing a database to analyze and develop criteria based
on time and temperature for a service life program to be used by all
utilities. The NRC staff is following the above industry activities and will
evaluate whether additional NRC actions are necessary.
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.
riginal gned by
8rian K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: Floyd S. Cantrell, RII
(404) 331-5534 Arnold J. H. Lee, NRR
(301) 504-2758 Attachment:
List of Recently Issued NRC Information Notices
- forwarded by JRJohnson memorandum to BKGrimes dated 3/8/94 see previous concurrence
OFFICE *Region II *Region II *Region II *OGCB/NRR
NAME FSCantrell DMVerrelli JRJohnson RJKiessel
[ DATE 3/ 8/94 3/ 8/94 3/ 8/94 4/19/94 OFFICE *Tech Editor *EMEB/NRR *EMEB/NRR *DE/NRR
NAME MFMejac AJHLee JANorberg BWSheron
DATE 4/19/94 4/21/94, 4/22/94 5/17/94 OFFICE OGCB/NRR =
NAME AJKugler* i s I
DATE 5/25/94 06/Zf(/94 Document Name: 94-48.IN
IN 94-xx
May xx, 1994 PSA and SNUG are establishing a database to analyze and develop criteria based
on time and temperature for a service life program to be used by all
utilities. Both of these organizations recognize that high temperatures seem
to be the leading cause of lubrication breakdown in snubbers. The NRC staff
is following the above industry activities closely and will take appropriate
regulatory actions deemed necessary.
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: Floyd S. Cantrell, Region II
(404) 331-5534 Arnold J. H. Lee, NRR
(301) 504-2758 Attachment: List of Recently Issued NRC Information Notices
- forwarded by JRJohnson memorandum to BKGrimes dated 3/8/94 see previous concurrence
OFFICE *Region II *Region II *Region II *OGCB/NRR
NAME FSCantrell DMVerrelli JRJohnson RJKiessel
DATE 3/ 8/94 3/ 8/94 3/ 8/94 4/19/94 OFFICE *Tech Editor *EMEB/NRR *EMEB/NRR *DE/NRR
NAME MFMejac AJHLee JANorberg BWSheron
DATE 4/19/94 4/21/94 4/22/94 5/17/94 OFFICE OGCB/NRR DORS/NRR l l
NAME AJKugler BKGrimes
DATE 5/2 794 5/ /94 _
Document name: b:\KJK\NKLNb\NKL1N.441
IN 94-xx
April xx, 1994 utilities. Both of these organizations recognize that high temperatures seem
to be the leading cause of lubrication breakdown in snubbers.
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: Floyd S. Cantrell, Region II
(404) 331-5534 Arnold J. H. Lee, NRR
(301) 504-2758 Attachment: List of Recently Issued NRC Information Notices
- forwarded by JRJohnson memorandum to BKGrimes dated 3/8/94 see previous concurrence
OFFICE l*Region II l*Region II l*Region II l*OGCB/NRR
NAME FSCantrell DMVerrelli JRJohnson RJKiessel
DATE 3/ 8/94 3/ 8/94 3/ 8/94 4/19/94 VIU
OFFICE *Tech Editor EMEERRR k AE/ N
NAME MFMejac A ee r erg BWShero
DATE 4/19/94 4N-/94 4
4/t-94 4/ %94\
OFFICE OGCB/NRR DORS/NRR a___
NAME AJKugler BKGrimes
DATE 4/ /94 4/ /94 Document Name: b:\KJK\NKL1Nb\NKL1N.441
- forwarded by JRJohnson memorandum to BKGrimes dated 3/8/94 see previous concurrence
OFFICE *Region II *Region II *Region II OGCB/NRR A AA
NAME FSCantrell DMVerrelli JRJohnson RJKiessel
DATE 3/ 8/94 3/ 8/94 3/ 8/94 4//M/94 OFFICE Tech Editor EMEB/NRR [ EMEB/NRR l DE/NRR
NAME d A Jo+ JHL & JANorberg BWSheron
DATE 4/k?/94 4/'1/94 4/ /94 4/ /94 OFFICE OGCB/NRR DORS/NRR _
NAME AJKugler BKGrimes
DATE 4/ /94 4/ /94 Document Name: G:\RJK\NRCINS\NRCIN.441
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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)
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