One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier SystemsML031080038 |
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: |
05/28/1993 |
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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-93-041, NUDOCS 9305280011 |
Download: ML031080038 (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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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>. |
A~- I
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 May 28, 1993 NRC INFORMATION NOTICE 93-41: ONE HOUR FIRE ENDURANCE TEST RESULTS FOR
THERMAL CERAMICS KAOWOOL, 3M COMPANY FS-195 AND
3M4 COMPANY INTERAM E-50 FIRE BARRIER SYSTEMS
Addressees
for nuclear power
All holders of operating licenses or construction permits
reactors.
PurDose
information
The U.S. Nuclear Regulatory Commission (NRC) is issuing this tests for Thermal
notice to alert addressees to the results of fire endurance
(3M Company)
Ceramics Kaowool, Minnesota Mining and Manufacturing Company reviewed by
FS-195, and 3M Company Interam E-50 1-hour fire barrier systems
inspection. It is expected that
NRC inspectors during a reverification to their facilities
recipients will review the information for applicability
However, and consider actions as appropriate to avoid similar problems.requirements;
notice are not NRC
suggestions contained in this information
therefore, no specific action or written response is required.
Description of Circumstances
the staff stated it
In Generic Letter 92-08, "Thermo-Lag 330-1 Fire Barriers," that are used by
would evaluate other known fire barrier materials and systems to Appendix R
licensees to fulfill NRC fire protection requirements pursuant staff has started
to 10 CFR Part 50 of the Code of Fedefal Regulations. The Thermal
by vendors other than
its review of fire barriers manufactured barrier systems to
Science, Incorporated, to verify the capability of the fire
and to meet
adequately perform their 1-hour or 3-hour fire-resistive functions
stated ampacity derating values.
at the Salem
A reverification inspection was conducted by NRC inspectors Electric Company
Nuclear Generating Station, owned by Public Service Gas and fire
(the licensee), the week of May 17, 1993. NRC inspectors reviewed systems used by
endurance test results for the electrical raceway fire barrier same fire area.
the licensee to separate safe shutdown functions within the FS-195 and
The systems used were Thermal Ceramics Kaowool, 3M Company in the fire
3M Company Interam E-50. The fire test results, as documented summarized in
barrier qualification test reports, are discussed below and are
the attached table.
oPi I9305QY
PM, rtt oaesoet30a
9305280011
002098 N Pr4
8 z #
IN 93-41 May 28, 1993 Kaowool Fire Barrier
Thermal Ceramics, Inc., was formerly the Insulating Products Division
of
Babcock and Wilcox, Inc., of Augusta, Georgia. The licensee fire endurance
testing basis for Kaowool is a Babcock and Wilcox fire test report
October 24, 1978. of
According to the report, five specimens of the Kaowool
barrier were tested on cable trays in a small-scale furnace. The maximum
length of the 45.7 cm [18 inch] wide cable trays was 61 cm [24 inches].
fill ranged from 33 percent to 35 percent. According to the report, Cable
test acceptance criterion was circuit integrity. The tests were not the fire
or controlled by an independent testing laboratory. conducted
The test report stated that the circuit integrity in one circuit was
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 1 minute. It also stated that cable temperatures exceeded lost at
[250 OF] above ambient air temperature in about 22 minutes. At 60 minutes 139 OC
into the test, the cable temperature was about 426.5 *C [800 OF]. Hose
tests were not performed. The results section of the test report stated stream
cables in all tests exhibited signs of fire damage, such as charring. that
3M Company FS-195 Fire Barrier
The licensee fire endurance qualification testing basis for the 3M Company
FS-195 fire.barrier system is a 3M Company test report of October 31, Test acceptance criteria were not reported. The report stated that 1980.
small-scale test at the 3M test facility. The figure in the report this was a
the test specimen was conceptual and did not give dimensions. According showing
the figure, the fire barrier was constructed by placing a cable tray to
metal air duct with the tray support in the middle of the duct. in a
The metal
duct was covered with FS-195, there was an air space- around the cable
and the tray contained 40 percent cable fill. tray, According to the test report, the metal duct temperature on the unexposed
of the fire barrier material exceeded 139 'C [250 OF] above ambient side
30 minutes. At 60 minutes the temperature was 326.5 °C [620 OF]. in about
specimen was not subjected to a hose stream test. The condition ofThe test
at the end of the test was not reported. the cables
3M Companv Interam E-50 Fire Barrier
The licensee fire endurance qualification testing basis for the 3M
Interam E-50 fire barrier system is a Twin City Testing Corporation Company
report of September 1986. The fire test acceptance criterion was test
circuit integrity as specified by American Nuclear Insurers. stated as
According to the test report, the cable tray test specimen was a 61
[24 inch] wide aluminum cable tray installed in the test slab in cm
configuration. The vertical drops into the furnace were 58.4 cm a horseshoe
[23 inches],
and the horizontal run'was 86.4 cm [34 inches]. The tray configuration
divided into four segments. A vertical run of solid bottom tray was
to a ladder-back 90o radial bend. This bend was connected to a was connected
tray segment, which was connected to a vertical ladder-back tray solid bottom
segment. The
IN 93-41 May 28, 1993 test specimen also included an air drop. One half of the tray had 14 percent
cable fill. The other half had 40 percent cable fill. A second test specimen
consisted of one 12.7 cm [5 inch] diameter steel conduit and one 12.7 cm
[5 inch] diameter aluminum conduit and a 25.4 cm [10 inch] by 25.4 cm
[10 inch] by 15.2 cm [6 inch] junction box.
The fire barrier installation procedures appended to the test report specified
multiple installation methods. However, the fire barrier construction details
and methods of fire barrier application for the test specimens were not
documented in the test report.
The temperatures within the fire barrier and the condition of the cables at
the end of the test were not reported.
As a result of the issues raised during the inspection, the licensee posted
fire watches as compensatory measures in accordance with plant procedures.
Discussion
The staff is continuing its review of these fire barrier systems including a
reassessment of any previous staff reviews of these systems. The staff
previously requested additional information on Kaowool from Thermal Ceramics, Incorporated, in a letter of April 27, 1993, and on the 3M fire barrier
systems from 3M Company in a letter of May 4, 1993. The staff will evaluate
whether further generic communications are needed to address the issues
discussed above.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact 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: Pat Madden, NRR
301-504-2854 Attachments:
1. Summary of Test Results
2. List of Recently Issued Information Notices
Attachment 1 IN 93-41 May 28, 1993 Page l.of 1 Summary of Test Results
Scale of test Small-scale Small-scale Small-scale
Test laboratory Not independent Not independent Not independent, but witnessed by
Twin City
_ _Testing Corp.
Hose stream test Not performed Not performed Performed
Cable damage Charred Unknown Unknown
Tested Not Not Not
configuration representative of representative of representative
in-plant in-plant of in-plant
configurations configurations configurations2 Maximum -426.5 C 326.5 eC[620 OF] Unknown
temp rature at 1 [-800 OF]
hour
Comments Accepted by NRC Accepted by NRC Installed in
11/20/1979 3/18/1981 1991; not
submitted to NRC
1 In a letter of May 18, 1993, to the NRC, the 3M Company stated that the
FS-195 fire barrier system is used only at Salem.
2 3M Company provided additional test reports to the licensee on
May 20, 1993. The licensee is evaluating the applicability of these test
reports to the in-plant configurations.
3 NRC acceptance criteria is 139 eC [250 OF] above ambient.
KQ~
Attachment 2 IN 93-41 May 28, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Subject Issuance Issued to
Notice No.
Fire Endurance Test 05/26/93 All holders of OLs or CPs
93-40 for nuclear power reactors.
Results for Thermal
Ceramics FP-60 Fire
Barrier Material
93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs
Power Reactor Biolog- for nuclear power reactors.
ical Shields
Inadequate Testing of 05/24/93 All holders of OLs or CPs
93-38 for nuclear power reactors.
Engineered Safety
Features Actuation
System
Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs
93-37 for nuclear power reactors.
minate Properties In- stalled in Limitorque
Valve Operator Housing
Covers
Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
93-36 Commission medical
and Records of Misadmin- istrations licensees.
Insights from Common- 05/12/93 All holders of OLs or CPs
93-35 for nuclear power plants
Cause Failure Events
(NPPs).
Potential for Loss of 05/06/93 All holders of OLs or CPs
93-34, for nuclear power reactors.
Supp. 1 Emergency Cooling
Function Due to A
Combination of
operational and Post- Loca Debris in Contain- ment
OL - Operating License
CP - Construction Permit
failiN
93-41 May 28, 1993 percent
test specimen also included an air drop. One half of the tray had 14 specimen
cable fill. The other half had 40 percent cable fill. A second test
cm
consisted of one 12.7 cm [5 inch] diameter steel conduit and one 12.7 cm [10 inch] by 25.4 cm
[5 inch] diameter aluminum conduit and a 25.4
[10 inch] by 15.2 cm [6 inch] junction box.
specified
The fire barrier installation procedures appended to the test report details
multiple installation methods. However, the fire barrier construction
for the test specimens were not
and methods of fire barrier application
documented in the test report.
at
The temperatures within the fire barrier and the condition of the cables
the end of the test were not reported.
As a result of the issues raised during the inspection, the licensee posted
fire watches as compensatory measures in accordance with plant procedures.
Discussion
a
The staff is continuing its review of these fire barrier systems including
reassessment of any previous staff reviews of these systems. The staff
previously requested additional information on Kaowool from Thermal Ceramics, Incorporated, in a letter of April 27, 1993, and on the 3M fire barrier
systems from 3M Company in a letter of May. 4, 1993. The staff will evaluate
whether further generic communications are needed to address the issues
discussed above.
If
This information notice requires no specific action or written response.
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager. Original signed by
Brian K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: Pat Madden, NRR
301-504-2854 Attachments:
1. Summary of Test Results
2. List of Recently Issued Information Notices
- SPLB:DSSA *DD:DSSA *D:DSSA *SPLB:DSSA *SPLB:DSSA *Tech Ed.
CMcCracken MVirgilio AThadani JHolmes SWest MMejac
5/27/93 5/ 5/27/93 5/27/93 5/27/93 5/27/93
GMarcus es
5/27/93 eg/93 DOCUMENT NAME: 93-41.IN
The temperatures within the fire barrier and the condition of the cables at
the end of the test were not reported.
The licensee opted to treat its fire barriers as indeterminate and posted fire
watches as compensatory measures in accordance with plant procedures after
discussing the reported fire test results with the NRC inspectors.
Discussion
The staff is continuing its review of these fire barrier systems including a
reassessment of any previous staff reviews of these systems. The staff
previously requested additional information on Kaowool from Thermal Ceramics, Incorporated in a letter of April 27, 1993, and on the 3M fire barrier systems
from 3M Company in a letter of May 4, 1993. The staff will evaluate if
further generic communications are needed to address the issues discussed
above.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact 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: Pat Madden, NRR
301-504-2854 Attachments:
1. Summary of Test Results
2. List of Recently Issued Information Notices
e' t .
SPLB:DSSA D A D:D J SP 6tDSSA SPLB:DSSA Tech Ed. ;
CMcCracken MViril io AThad ni JHolmes SWest MMejac aV%.
5- 7/93 c5 /lZ93 5/z7/93 5/)+/93 5/2 /93 f
OGCB:DORS D: DORS
GMarcusqM BGrimes
S/.27/9?3 / /93
[G:\THERMOLA\OTHERVEN\IN 3ME50. []
Originator: Jeff Holmes-
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list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
... further results |
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