Vulnerability of Emergency Diesel Generators to Fuel Oil/Lubricating Oil IncompatibilityML031050485 |
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: |
12/19/1996 |
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From: |
Martin T Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-96-067, NUDOCS 9612160113 |
Download: ML031050485 (7) |
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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>. |
~' <>ov
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 December 19, 1996 NRC INFORMATION NOTICE 96-67: VULNERABILITY OF EMERGENCY DIESEL
GENERATORS TO FUEL OIL/LUBRICATING OIL
INCOMPATIBILITY
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 a recent finding involving degradation of the power block assembly of two
emergency diesel generators caused by an incompatibility of the lubricating oil with fuel oil
with a low sulfur content. It is expected that recipients will review the information for
applicability and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this notice do not constitute NRC requirements; therefore, no
specific action or written response is required.
DescriDtion of Circumstances
In December 1995, during preoperational testing of a new safety-related emergency diesel
generator (EDG), test engineers for the licensee, Baltimore Gas and Electric Company
(BGE), at the Calvert Cliffs Nuclear Power Plant, noted sporadic spikes in crankcase
pressure and lubricating oil seeping out from the crankshaft seal. The engine was shut down
and BGE conducted a boroscopic inspection of the unit. One cylinder showed indications of
abnormal wear. The cylinder liner, piston, and piston rings were removed for analysis and
replaced with a spare set. The testing program resumed, with normal crankcase parameters
being indicated.
The test program for the safety-related EDG was completed on January 8, 1996. Several
days later, during a scheduled 2-year maintenance inspection, BGE found four cylinders with
heavy carbon-like deposits on the pistons and behind the piston rings and evidence of
abnormal scuffing on the cylinder liners. On further inspection, all the cylinders exhibited
some degree of similar degradation, including the replacement cylinder. BGE then inspected
a second new EDG that had been installed as a backup power supply in 1995 for station
blackout. One cylinder on the station blackout engine exhibited degradation similar to that of
the safety-related EDG. Upon disassembly, excessive carbon deposition was found in all
cylinders.
9612160113 G96R 7-00 9614?
IN 96-67 December 19, 1996 Discussion
Calvert Cliffs Nuclear Power Plant comprises two Combustion Engineering reactors with three
EDGs, one dedicated to each unit and the third a "swing" EDG, that automatically loads onto
the accident unit. In 1989, BGE initiated a modification to upgrade Calvert Cliffs emergency
electrical system and meet the requirements of the station blackout rule. The modification
included the installation of one safety-related EDG (giving each unit two dedicated EDGs)
and one nonsafety-related EDG capable of powering any of the four safety-related 4-kV
emergency electrical buses (for station blackout purposes). The new EDGs are basically
identical, each with two engines in tandem with the generator between the engines. The
EDGs were manufactured by Societ6 Alsacienne de Constructions M6chaniques de Mulhouse
(SACM) and have a nominal continuous rating of 5400 kW.
When the cylinder degradation was found, BGE assembled a root cause analysis team, which
included persons with recognized industry expertise. The team developed three potential
causes for the diesel power block degradation: components not to design specifications, improper operation of the engines, and lubricating oilfuel oil incompatibility. The first
possibility was ruled out by metallurgical and dimensional analysis and the second from
discussions with SACM and other operators of SACM diesel generators. The team
concluded that the lubricating oil used was incompatible with low sulfur content fuel.
The BGE team found that lubricating oil compatibility depends, in part, on the type of fuel
being burned, as the lubricating oil contains an additive package that neutralizes the products
of combustion, most importantly sulfuric acid, to prevent engine corrosion. The lubricating oil
originally selected was an American Petroleum Institute (API) CD-grade synthetic oil. For the
fuel oil used in the engines at that time, the specification was that the sulfur content was not
to exceed 0.30 percent. In early 1995, the supplier of fuel oil to Calvert Cliffs switched to
fuels with sulfur contents of 0.05 percent or less in order to meet new Environmental
Protection Agency requirements intended to reduce sulfuric acid emissions. With the
reduced amount of sulfur, there would be more unreacted additive in the lubricating oil, resulting in the formation of deposits when some of the oil was bumed. These deposits built
up behind the piston rings, forcing the rings to extrude and come into contact with the
cylinder liner wall, resulting in scuffing.
After the problem was identified, BGE rebuilt the safety-related EDG with new cylinder liners, pistons, and piston rings. On the basis of the findings of the root cause analysis team, the
safety-elated EDG was supplied with a different lubricating oil, which is an API CG-4 grade
mineral-based oil. A series of acceptance tests were then run to validate the root cause.
The safety-related EDG was inspected after test runs totaling about 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> and no
abnormal conditions were found. The station blackout EDG was then refurbished, tested, and inspected, and the results were identical to those for the safety-related EDG.
Another characteristic of synthetic lubricating oil was identified during the review of this event.
Synthetic oils contain diester additives required to improve solubility of oil additives. In diesel
IN 96-67 December 19, 1996 engines with low oil sump temperatures, water may accumulate in the sump because the
temperature is too low to vaporize it. This water might cause hydrolysis of the diesters and
the resulting acids would react with calcium in the additive to form insoluble compounds
(soaps). These compounds may clog filters and degrade performance of a diesel engine.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please refer to the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Kirke Lathrop, Region I
(410) 586-2626 Email: hkl@nrc.gov
Krzysztof Parczewski, NRR
(301) 415-2705 Email: kip@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
KI %&
Attachment
IN 96-67 December 19, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-66 Recent Misadministrations 12/13/96 All U.S. Nuclear
Caused by Incorrect Cali- Regulatory Commission
brations of Strontium-90 Medical Use Licensees
Eye Applicators authorized to use
strontium-90 (Sr-90)
eye applicators
96-65 Undetected Accumulation 12/11/96 All holders of OLs
of Gas in Reactor Coolant or CPs for nuclear
System and Inaccurate power reactors
Reactor Water Level
Indication During Shutdown
96-64 Modifications to Con- 12/10/96 All holders of OLs
tainment Blowout Panels or CPs for nuclear
Without Appropriate reactors
Design Controls
96-63 Potential Safety Issue 12/05/96 All U.S. Nuclear
Regarding the Shipment Regulatory Commission
of Fissile Material licensees authorized
to possess special
nuclear material in
unsealed quantities
greater than a critical
mass
96-62 Potential Failure of the 11/20/96 All holders of OLs
Instantaneous Trip Function and CPs for nuclear
of General Electric RMS-9 power plants
Programmers
96-61 Failure of a Main Steam Safety 11/20/96 All holders of OLs or
Valve to Reseat Caused by an CPs for nuclear power
Improperly Installed Release reactors
Nut
OL = Operating License
CP = Construction Permit
IN 96-67 December 19, 1996 engines with low oil sump temperatures, water may accumulate in the sump because the
temperature is too low to vaporize it. This water might cause hydrolysis of the diesters and
the resulting acids would react with calcium in the additive to form insoluble compounds
(soaps). These compounds may clog filters and degrade performance of a diesel engine.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please refer to the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
original signed by
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Kirke Lathrop, Region I
(410) 586-2626 Email: hkl@nrc.gov
Krzysztof Parczewski, NRR
(301) 415-2705 Email: kipenrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 11/13/96 A*aC4't J-- 6J cZ'JAcC4Lr
DOCUMENT NAME: 96-67.IN *SEE PREVIOUS CONCURRENCES
OFFICE Contacts C/EMCB:DE C/PECB:DRPM D/DRPl l
NAME KLathrop* JStrosnider* AChaffee* TM
KParzewski*
II5 DATE 11/21/96 111/21/96 12/12/96 120Y96 UOicial Kecord Copy r PD C)
4xlk
10 A-'J6
IN 96-xx
December xx, 1996 engines with low oil sump temperatures, water may accumulate in the sump because the
temperature is too low to vaporize it. This water might cause hydrolysis of the diesters and the
resulting acids would react with calcium in the additive to form insoluble compounds (soaps).
These compounds may clog filters and degrade performance of a diesel engine.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please refer to the technical contacts listed
below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Kirke Lathrop, Region I
(410) 586-2626 Email: hkl@nrc.gov
Krzysztof Parczewski, NRR
(301) 415-2705 Email: kip@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor reviewed 11/13/96 DOCUMENT NAME: G:JRT\EDG.INS *SEE PREVIOUS CONCURRENCES
OFFICE Contacts C/EMCB:DE C/PECB:DRPM
KLathrop* JStrosnider* AChaffee TMzinl
NAME
KParzewski* lI _
DATE 11/21/96 11/21/96 1.Vlt/96 124096 MIciaal Kecora C.opy
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rAc0
4 IN 96-xx
November xx, 1996 abnormal conditions were found. The station blackout EDG was then refurbished, tested and inspected, with identical results as the safety-related EDG.
Another undesirable characteristic of synthetic lubricating oil was identified
during the review of this event. Synthetic oils contain diester additives
required to improve solubility of oil additives. In diesel engines with low
oil sump temperatures, water may accumulate in the sump because the temperature
is too ow to vaporize it. This water may cause hydrolysis of the diesters and
the resulting acids react with calcium in the additive to from insoluble
compounds (soaps). These compounds may clog filters and degrade performance of
a diesel engine.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please refer to
the technical contact listed below or the appropriate Office of Nuclear Reactor
Regulation (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical Contact:
Kirke Lathrop, RI
(410) 586-2626 Internet:hkl@nrc.gov
Krzysztof Parczewski, NRR
(301) 415-2705 Internet:kip@nrc.gov
Attachment:
1. List of Recently Issued NRC Information Notices
Tech Editor reviewed 11/13/96 47 DOCUMENT NAME: G:\JRT\EDG.INS 1 OFFICE Contacts C/EMC E .DC/PECB:DRPM D/D
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KParzewsk iV F._
AChaffee
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DATE 11/h3/96 11/P.J/96 11/ /96 1+/-/93/96 Official Record Copy
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip, Overspeed)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Commercial Grade, Troxler)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996, Topic: Hardened grease)
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