Erroneous Data from Defective Thermocouple Results in a FireML031060060 |
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: |
05/24/1996 |
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From: |
Cool D, Teneyck E NRC/NMSS/FCSS, NRC/NMSS/IMNS |
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To: |
|
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References |
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IN-96-033, NUDOCS 9605220019 |
Download: ML031060060 (8) |
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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>. |
11 -I
UNITED STATES
NUC EAR REGULATORY COMMISSION
OFFICE OF NUC EAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 May 24, 1996 NRC INFORMATION NOTICE 96-33: ERRONEOUS DATA FROM DEFECTIVE THERMOCOUPLE
'RESULTS IN A FIRE
Addressees
All material and fuel cycle licensees that monitor temperature with
thermocouples.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to an incident where a defective thermocouple
caused an evaporator to run at an excessively high temperature, resulting in a
fire. It is expected that recipients will review the information for applica- bility to their facilities and consider actions, as appropriate, to avoid
similar problems. However, suggestions in this information notice are not NRC
requirements; therefore, no specific action nor written response is required.
Description of Circumstances
On February 21, 1996, a licensee had a fire in the ventilation system of its
liquid waste process. The licensee's investigation determined that the fire
was caused by a type-J thermocouple manufactured with reverse polarity. The
type-J thermocouple was part of a Pulse Combustion Drier put into operation in
1985 to evaporate waste water. The drier operates with natural gas that
ignites inside the drier combustion chamber. Waste water is pumped into the
hot gases being expelled from the combustion chamber within an evaporation
cone. The temperature is controlled by regulating the amount of waste water
being fed into the system. This is based on temperature readings from a
thermocouple in the duct work.
The licensee had replaced the thermocouple with a spare unit while trouble- shooting a lead wire problem on February 15, 1996. The spare thermocouple was
found to have reverse polarity during a test run, and the licensee believed it
had corrected the problem by reversing the lead wire polarity at the
instrument. The system appeared to read correctly during a 10-minute test
run. However, approximately an hour into a full run the next day, the
temperature reading began to behave erratically. The temperature readings
dropped even though the actual temperature was increasing. By the time the
licensee identified the discrepancy, a fire had started in the dust collector- filter cartridges.
The defective type-J thermocouple was purchased in 1985 (as a spare part),
along with the Pulse Combustion Drier from Sonodyne Industries in Portland, Oregon. The thermocouple had been manufactured for Sonodyne Industries by
~~20O1 l Qdjoto
pi)t TE-E Aon 96-033-9(052c/
IN 96-33 May 24, 1996 Gulton Measurement and Control Systems Division (a division of Gulton
Industries) in East Greenwich, Rhode Island. The licensee reported that
Sonodyne Industries is out of business and Gulton Industries is no longer
manufacturing thermocouples.
Discussion
NRC is not aware of any other Sonodyne driers currently being used by NRC
licensees. Licensees that operate waste water evaporators or other heat- generating systems using thermocouples may wish to consider reviewing the
source of the thermocouples and testing the polarity of thermocouples in
stock.
This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate regional office.
ElizaI~%h Q. T6 ck, Di tctor Donald A. Cool, Director
Divis ton of Fuel Cycle Safety Division of Industrial and
and Safeguards Medical Nuclear Safety
Office of Nuclear Material Safety Office of Nuclear Material Safety
and Safeguards and Safeguards
Technical contact: Kevin M. Ramsey, NMSS
(301) 415-7887 Internet:kmrenrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. lst of Recently Issued NRC Information s
P"&t' &-
A
Ki)
K-,
Attachment 1 IN 96-33 May 24, 1996 LIST OF RECENTLY ISSUED
NHSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-28 Suggested Guidance Relat- 05/01/96 All material and fuel cycle
1ng to Development and licensees
Implementation of Correc- tive Action
96-21 Safety Concerns Related 04/10/96 All NRC Medical Licensees
to the Design of the Door authorized to use brachy- Interlock Circuit on therapy sources in high- Nucletron High-Dose Rate and pulsed-dose-rate remote
and Pulsed Dose Rate
Remote Afterloading Brachy- therapy Devices
96-20 Demonstration of Associ- 04/04/96 All industrial radiography
ated Equipment Compliance licensees and radiography
with 10 CFR 34.20 equipment manufacturers
96-18 Compliance With 10 CFR 03/25/96 All material licensees
Part 20 for Airborne authorized to possess and
Thorium use thorium in unsealed form
96-04 Incident Reporting 01/10/96 All Radiography Licensees
Requirements for and Manufacturers of
Radiography Licensees Radiography Equipment
95-58 10 CFR 34.20; Final 12/18/95 Industrial Radiography
Effective Date Licensees.
Handling Uncontained 12/6/95 All Uranium Recovery
Yellowcake Outside of a Licensees.
Facility Processing Circuit
95-51 Recent Incidents Involving 10/27/95 All material and fuel cycle
Potential Loss of Control licensees.
of Licensed Material
95-50 Safety Defect in Gammamed 10/30/95 All High Dose Rate
121 Bronchial Catheter Afterloader (HDR) Licensees.
Clamping Adapters
I2
3. Attachment 2 IN 96-33 May 24, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-32 Implementation of 10 CFR 05/23/96 All holders of OLs or CPs
50.55a(g)(6)(ii)(A), for nuclear power reactors
Augmented Examination
of Reactor Vessel'
96-31 Cross-Tied Safety Injec- 05/22/96 All holders of OLs or CPs
tion Accumulators for pressurized water
reactors
96-30 Inaccuracy of Diagnostic 05/21/96 All holders of OLs or CPs
Equipment for Motor- for nuclear power reactors
Operated Butterfly Valves
96-29 Requirements in 10 CFR 05/20/96 All holders of OLs or CPs
Part 21 for Reporting and for nuclear power reactors
Evaluating Software Errors
96-28 Suggested Guidance Relating 05/01/96 All material and fuel cycle
to Development and Imple- licensees
mentation of Corrective
Action
96-27 Potential Clogging of High 05/01/96 All holders of OLs or CPs
Pressure Safety Injection for pressurized water
Throttle Valves During reactors
Recirculation
96-26 Recent Problems with Over- 04/30/96 All holders of OLs or CPs
head Cranes for nuclear power reactors
96-25 Transversing In-Core Probe 04/30/96 All holders of OLs or CPs
Overwithdrawn at LaSalle for nuclear power reactors
County Station, Unit 1
96-24 Preconditioning of Molded- 04/25/96 All holders of OLs or CPs
Case Circuit Breakers for nuclear power reactors
Before Surveillance Testing
OL - Operating License
CP - Construction Permit
J
11--.11 IN 96-33 May 24, 1996 Gulton Measurement and Control Systems Division (a division of Gulton
Industries) in East Greenwich, Rhode Island. The licensee reported that
Sonodyne Industries is out of business and Gulton Industries is no longer
manufacturing thermocouples.
Discussion
NRC is not aware of any other Sonodyne driers currently being used by NRC
licensees. Licensees that operate waste water evaporators or other heat- generating systems using thermocouples may wish to consider reviewing the
source of the thermocouples and testing the polarity of thermocouples in
stock.
This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate regional office.
Elizabeth Q. Ten Eyck, Director Donald A. Cool, Director
Division of Fuel Cycle Safety Division of Industrial and
and Safeguards Medical Nuclear Safety
Office of Nuclear Material Safety Office of Nuclear Material Safety
and Safeguards and Safeguards
Technical contact: Kevin M. Ramsey, NMSS
(301) 415-7887 Internet:kmr~nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: 96-33.IN
- SEE PREVIOUS CONCURRENCE -O
IMOB* C NMSS* I IMOB* lCSS I FCSS4I IMNS I
NAME KRamsey/kr/ll EKraus CHaney PTing ETentyck
DATE 4/15/96 4/15/96 4/18/96 4/18/96 5/15/96 5/16/96 j
OFFICIAL RECORD COPY
l)
IN 96- April , 1996 Gulton Measurement and Control Systems Division (a division of Gulton
Industries) in East Greenwich, Rhode Island. The licensee reported that
Sonodyne Industries is out of business and Gulton Industries is no longer
manufacturing thermocouples.
Discussion:
NRC is not aware of any other Sonodyne driers currently being used by NRC
licensees. Licensees that operate waste water evaporators or other heat- generating systems using thermocouples may wish to consider reviewing the
source of the thermocouples and testing the polarity of thermocouples in
stock.
This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate regional office.
Elizabeth Q. Ten Eyck, Director Donald A. Cool, Director
Division of Fuel Cycle Safety Division of Industrial and
and Safeguards Medical Nuclear Safety
Office of Nuclear Material Safety Office of Nuclear Material Safety
and Safeguards and Safeguards
Contact(s): Kevin M. Ramsey, NMSS
(301) 415-7887 Attachments:
1. Lis t of Recently Issued NMSS Information Notices
2. Lis,t of Recently Issued NRC Information Notices
DOCUMENT NAME: G:INTHERMO.KMR
OFC I 0B* I _ NMSS* I IMOB* IjI FCSS I IM A
NAME KRamsey/kr/ll EKraus CHaney PTinETen k
DATE 4/15/96 - 4/15/96 m4/18/96 4//j'96 OFFICIAL RECORD COPY
FN 96- April , 1996 Page 2 of 2 Gulton Measurement and Control Systems Division (a division of G ton
Industries) in East Greenwich, Rhode Island. The licensee rep ted that
Sonodyne Industries is out of business and Gulton Industries s no longer
manufacturing thermocouples.
Discussion:
NRC is not aware of any other Sonodyne driers curren y being used by NRC
licensees. Licensees that operate waste water evap rators or other heat- generating systems using thermocouples may wish t consider reviewing the
source of the thermocouples and testing the pol ity of thermocouples in
stock.
This information notice requires no specifi action nor written response. If
you have any questions about the informat n in this notice, please contact
the technical contact listed below or th appropriate regional office.
Donald A. Cool, Director
.Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Contact(s): Kevin M. msey, NMSS
(301) 41 7887 Attachments:
1. List of Recenty Issued NMSS Information Notices
2. List of Rec tly Issued NRC Information Notices
DOCUMENT NAME: G: THERMO.KMR
lOFC l- IMW l lNMSS* I l1I40B I FCSS l l IMNS I
NAME KR seylkrll1 EKraus Haney PTing DCool
DATE 4/15/96 4/15/96 4//K/96 4/ /96 4/ /96 j
OFFICIAL RECORD COPY
IN 96- April , 1996 Gulton Measurement and Control Systems Division (a division of Gulton
Industries) in East Greenwich, Rhode Island. The licensee reported that
Sonodyne Industries is out of business and Gulton Industries is no longer
manufacturing thermocouples.
Discussion:
Based on licensee statements and NRC inspection experie, e the Pulse
Combustion Drier marketed by Sonodyne Industries did rj5 sell very well. NRC
is not aware of any other Sonodyne driers currently }Sing used by NRC
licensees. Licensees that operate waste water evap rators or other heat- generating systems using thermocouples may wish 14 consider reviewing the
source of the thermocouples and testing the po ity of thermocouples in
stock.
This information notice requires no specif c action nor written response. If
you have any questions about the informaCion in this notice, please contact
the technical contact listed below or e appropriate regional office.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Contact(s): Kevin4 . Ramsey, NMSS
2 1) 415-7887 Attachments;
1.Ls ~Recently Issued NMSS Information Notices
2. Li of Recently Issued NRC Information Notices
DOCUMENT X ME: G:INTHERMO.KMR
OFC IMOB l NMSS l IMOB Il FCSS I IMNS
NAME KRamseyr Eaus CHaney PTing l DCool
DATE[ 4/15/96 4/15/96 T 4/ /96 OFFICIAL RECORD COPY
4/ /96 [ 4/ /96
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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)
- 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: 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)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- 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: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- 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)
- 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: Nondestructive 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)
- 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, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- 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)
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