Use of Inappropriate Lubrication Oils in Satety-Related ApplicationsML031070496 |
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: |
06/10/1993 |
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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-93-043, NUDOCS 9306040105 |
Download: ML031070496 (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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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 10, 1993 NRC INFORMATION NOTICE 93-43: USE OF INAPPROPRIATE LUBRICATION OILS IN
SAFETY-RELATED APPLICATIONS
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
PurDose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to a potential for introducing inappropriate
lubricating oils into safety-related components. 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
During routine surveillance of plant equipment at the Farley nuclear plant in.
June-July 1992, the operations staff discovered that lubricating oils for the
outboard and inboard bearings of component cooling water pump motors were
discolored. A closer examination revealed some brown sheen on the bearing and
other indications of bearing wear. The licensee analyzed samples of the
lubricating oils and determined that the oils were not of the viscosity
specified for that application.
The licensee subsequently sampled the lubrication oils in all plant safety- related equipment. Of 33 samples taken, .18 revealed the presence of an
inappropriate lubrication oil. In some cases, the correct oil was not
present; in others, the sample indicated that a mixture of the correct oil and
an incorrect oil was present.
Discussion
The licensee determined that, because of a wrong label on a drum supplied to
the licensee by the vendor, Texaco Regal R & 0 68 oil was used in safety- related applications where Texaco R & 0 32 oil was specified. The oil was
purchased as a commercial grade product. The licensee had not sampled the oil
when it was delivered to verify that it had received the oil it had ordered.
The licensee hired a consultant to evaluate the effect of having used the
R & 0 68 oil instead of the R & 0 32 oil. The consultant determined that no
serious problem was likely to occur in the short term, because the two oils
9306040105 ?3.-0q3
?DR~~n N_/f oJ£t +%c,93
IN 93-43 June 10, 1993 differed only in viscosity. All of the additives were identical.
the consultant also indicated that the more viscous oil (R & 0 68) However, would
generate more heat from higher friction. This could increase oxidation
oil, resulting in shorter oil lifetime. The higher viscosity might of the
bearing distress, which could lead to increased wear on the bearing. also cause
The licensee replaced the oil in all of the affected equipment, that the correct oil was being used. Further, the licensee has after assuring
instituted
procedures to ensure that oil is sampled upon receipt at the warehouse, release into the plant, and again before use. before
Appendix B to 10 CFR Part 50 contains the NRC regulations for procurement
quality assurance (QA) and quality control (QC) for products to
safety-related applications. Generic Letter (GL) 89-02, "Actionsbe used in
the Detection of Counterfeit and Fraudulently Marketed Products," to Improve
GL 91-05, "Licensee Commercial-Grade Procurement and Dedication and
Programs,"
discuss commercial-grade dedication and the characteristics of effective
procurement and dedication programs.
This information notice requires no specific action or written response.
you have any questions about the information in this notice, please If
the technical contacts listed below, or the appropriate Office of contact
Reactor Regulation (NRR) project manager. - Nuclear
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: George Maxwell, RII
(205) 899-3386 Michael Morgan, RII
(205) 899-3387 Todd A. Cooper, RII
(704) 875-1681 Attachment:
List of Recently Issued NRC Information Notices
-'S.,
Ki 4- Attachment
IN 93-43 June 10, 1993 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-42 Failure of Anti-Rotation 06/09/93 All holders of OLs or CPs
Keys in Motor-Operated for nuclear power reactors.
Valves Manufactured by
Velan
93-41 One Hour Fire Endurance 05/28/93 All holders of OLs or CPs
Test Results for Thermal for nuclear power reactors.
Ceramics Kaowool, 3M
Company FS-195 and
3M Company Interam E-50
Barrier Systems
93-40 Fire Endurance Test 05/26/93 All holders of OLs or CPs
Results for Thermal for nuclear power reactors.
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
93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs
Engineered Safety for nuclear power reactors.
Features Actuation
System
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs
minate Properties In- for nuclear power reactors.
stalled in Limitorque
Valve Operator Housing
Covers
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- Commission medical
istrations licensees.
93-35 Insights from Common- 05/12/93 All holders of OLs or CPs
Cause Failure Events for nuclear power plants
(NPPs).
OL - Operating License
CP - Construction Permit
IN 93-43 June 10, 1993 differed only in viscosity. All of the additives were identical. However, the consultant also indicated that the more viscous oil (R & 0 68) would
generate more heat from higher friction. This could increase oxidation of the
oil, resulting in shorter oil lifetime. The higher viscosity might also cause
bearing distress, which could lead to increased wear on the bearing.
The licensee replaced the oil in all of the affected equipment, after assuring
that the correct oil was being used. Further, the licensee has instituted
procedures to ensure that oil is sampled upon receipt at the warehouse, before
release into the plant, and again before use.
Appendix B to 10 CFR Part 50 contains the NRC regulations for procurement
quality assurance (QA) and quality control (QC) for products to be used in
safety-related applications. In addition, the NRC has provided further
guidance in Regulatory Guides 1.28, 1.33, and 1.123. These requirements and
guides, if properly implemented, provide a measure of assurance for the
suitability of products to be used in safety-related systems. Generic Letter
(GL) 89-02, "Actions to Improve the Detection of Counterfeit and Fraudulently
Marketed Products," and GL 91-05, "Licensee Commercial-Grade Procurement and
Dedication Programs," discuss commercial-grade dedication and the
characteristics of effective procurement and dedication programs.
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 contacts listed below, or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager. odginal signed by
Brian K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: George Maxwell, RII
(205) 899-3386 Michael Morgan, RII
(205) 899-3387 Todd A. Cooper, RII
(704) 875-1681 Attachment:
List of Recently Issued NRC Information Notices
- OGCB:DORS *RVIB:DRIL *PDI I-1 *DRP:RII *TechEd
TJKim LNorrholm JMitchell JJohnson RSanders
03/30/93 03/30/93 03/30/93 04/1 93 4/13/93
- OGCB:DORS *D/DRIL:NRR *D/DE/NRR t~RR
GHMarcus CRossi JRichardson
04/15/93 05/26/93 05/27/93 //93 Document Name: 93-43.IN
IN 93-XX
May xx, 1993 differed only in viscosity. All of the additives were identical. However, the consultant also indicated that the more viscous oil (R & 0 68) would
generate more heat from higher friction. This could increase oxidation of the
oil, resulting in shorter oil lifetime. The higher viscosity might also cause
bearing distress, which could lead to increased wear on the bearing.
The licensee replaced the oil in all of the affected equipment, after assuring
that the correct oil was being used. Further, the licensee has instituted
procedures to ensure that oil is sampled upon receipt at the warehouse, before
release into the plant, and again before use.
Appendix B to 10 CFR Part 50 contains the NRC's regulations for procurement
quality assurance (QA) and quality control (QC) for products to be used in
safety-related applications. addition, thCpro -furter
-guidanee-in ReWfatsty Guides-I &*1.33, and 1.312. h erqurmnsai-/f,;
guides, if properly implemented, provide a-eaureofassura
lt ~f uc i ety-related-systems. Generic Letter
(GL) 89-02, "Actions to Improve the Detection of Counterfeit and Fraudulently /
Marketed Products," and GL 91-05, "Licensee Commercial-Grade Procurement and
Dedication Programs," discuss commercial-grade dedication and the
characteristics of effective procurement and dedication programs.
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 contacts listed below, or the appropriate project manager in the
Office of Nuclear Reactor Regulation (NRR).
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contacts: George Maxwell, RII
(205) 899-3386 Michael Morgan, RII
(205) 899-3387 Todd A. Cooper, RII
(704) 875-1681 Attachment: List of Recently Issued NRC Information Notices
Document Name: INFONOT.KIM
- OGCB:DORS *RVIB:DRIL *PDII-1 *DRP:RII *TechEd
TJKim LNorrholm JMitchell JJohnson RSanders
03/30/93 03/30/93 03/30/9 04/12/93 04/13/93
/D/DORS:NRR
GHMarcus \Ri dsdn BGrimes
04/15/93 05/ 93 05 93 05/ /93 cIA
IN 93-XX
April xx, 1993 generate more heat from higher friction. This could increase oxidation of the
oil, resulting in shorter oil lifetime. The higher viscosity might also cause
bearing distress, which could lead to increased wear on the bearing.
The licensee replaced the oil in all of the equipment, after assuring that the
correct oil was being used. Further, the licensee has instituted procedures
to ensure that oil is sampled upon receipt at the warehouse, before release
into the plant, and again before use.
Many utilities are using the Electric Power Research Institute (EPRI) document
NP-5652, "Guideline for the Utilization of Commercial Grade Items in Nuclear
Safety Related Application," as the basis for a dedication process for
commercially procured materials. According to the EPRI document, the
utilization of commercial-grade items intended for safety-related application
involves two distinct processes: (1) a technical evaluation to assure that
requirements for an acceptable item are specified in the procurement document
and (2) acceptance methods to reasonably assure the item received is the item
that was specified.
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 contacts listed below, or the appropriate project manager in the
Office of Nuclear Reactor Regulation (NRR).
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: George Maxwell, RII
(205) 899-3386 Michael Morgan, RII
(205) 899-3387 Todd A. Cooper, R11
(704) 875-1681 Attachment: List of Recently Issued NRC Information Notices
Document Name: INFONOT.KIM
- OGCB:DORS *RVIB:DRIL *PDII-1 *DRP:RII *TechEd
TJKim LNorrholm JMitchell JJohnson RSanders
03/30/93 03/30/93 03/30/93 04/12/93 04/13/93 OGCB:DORS D/DORS:NRR
GHMarcus,5 BGrimes 6
04/aS/93 04/ /93T
Document Name: INFONOT.KJ
OGCB:DVJ PD II- Ž6t?%-1 DRP:RI I TechEd
TJKim LR~Ltm
JMitchell JJohnson JMain Vaou*J44
038/0 03 f93 03/3n93 *12/93 OGCB:DORS D/DORS:NRR
6cY/la/l 5
GHMarcus BGrimes
03/ /93 03/ /93
x( VLih* LA-tng
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 project manager in the Office of Nuclear
Reactor Regulation (NRR).
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical Contacts: George Maxwell, RII
(205) 899-3386 Michael Morgan, RII
(205) 899-3387 Todd A. Cooper, RII
(704) 875-1681 Attachments: List of Recently Issued NRC Information Notices
OGCB:D QRS DRP:RII TECH ED
TJKim JJohnson JMain Ri"W&Ae 4d
03/// 93 03/ /93 O3+-f9e
0/I3/f 3 OGCB:DORS DORS
GMarcus BGrimes
03/ /93 03/ /93
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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)
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