Incorrect Effective Diaphragm Area Values in Vendor Manual Result in Potential Failure of Pneumatic Diaphragm ActuatorsML031050477 |
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: |
12/19/1995 |
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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-96-068, NUDOCS 9612160116 |
Download: ML031050477 (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>. |
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 December 19, 1996 NRC INFORMATION NOTICE 96-68: INCORRECT EFFECTIVE DIAPHRAGM AREA
VALUES IN VENDOR MANUAL RESULT IN
POTENTIAL FAILURE OF PNEUMATIC DIAPHRAGM
ACTUATORS
Addressees
All holders of operating licenses or construction permits for nuclear power reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to the fact that some vendors have published incorrect values for effective
diaphragm area for some spring-type pneumatic diaphragm actuators and that use of these
incorrect values may result in safety-related air-operated valves not fully closing under design
basis conditions. 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
On October 4, 1996, Commonwealth Edison, licensee for the LaSalle County Station, issued
a notification puisuant to 10 CFR Part 21 (Accession No. 9610080102). The notification
identified the deficiency as incorrect values for the effective diaphragm areas, as published
by the original and current valve vendors, for certain models of pneumatic actuators.
The original valve vendor, Black, Sivalls, and Bryson (13S&B), was later purchased by
WKM Valve Division of ACF Industries, then by Muesco, and by Anchor/Darling Valve
Company. The affected model of actuator is the Model 70-13 pneumatic diaphragm actuator, sizes 35, 70, 140, and 280. The size refers to the published diaphragm area in square
inches. The affected actuators are either direct acting (extends the valve stem when air
pressure is applied) or reverse acting (retracts the stem when air is applied) spring return
actuators.
The Part 21 notification included an attachment providing a Nuclear Plant Reliability Data
System (NPRDS) listing of valves of the applicable model number by plant; however, the
listing may not include all of the applicable valves and may include valves that are not safety
related or that are not required to isolate as are the primary containment isolation
9612160116 `l
D _,_j A
IN 96-68 December 19, 1996 valves at the LaSalle County Station. Some of the valves listed are not diaphragm actuated
valves and the identification of some items is incomplete. The present manufacturer, Anchor/Darling Valve Company, was unable to compile a complete listing of the actuator
applications because purchase order records from the original vendor are unavailable.
Discussion
The licensee found discrepancies in the bench set values of the actuators during the LaSalle
County Station refueling outage that took place from February through April 1996. The
published bench set and the actual bench set values, indicated from testing by the plant
mechanics, were inconsistent. "Bench set" refers to the amount of preload and final
compression force placed on the actuator spring so that the applied spring force on loss of
air will achieve the required travel of the valve stem. Bench set adjustments are made by
applying air pressure to the actuator in accordance with the manufacturer's published values
and adjusting the spring compressive force by means of an adjusting screw to achieve the
desired relationship between air pressure and valve stem travel. When performing bench set
testing, incomplete valve stroke is typically indicative of a stiffer-than-expected spring.
However, testing by the licensee indicated that the springs were within manufacturer's
tolerances and additional testing with a known spring force, a known air supply pressure, and
a known load indicated that the actual effective diaphragm area, which relates to the force
opposing the spring as well as to the compression of the spring for proper preloading, was
less than the published values.
Anchor/Darling Valve Company was contacted by the licensee and performed a series of
tests to determine the actual effective diaphragm area. These tests indicated that the actual
diaphragm areas of the various sizes of the Model 70-13 actuators were approximately
90 percent of the published values. Further testing by the licensee uncovered a contributing
problem that further reduced the effective diaphram area. The diaphragm case consists of
two halves bolted together. Generally one half is deeper than the other. It was discovered
that reverse-acting actuators assembled with a deep upper half caused unintended stretching
of the diaphragm within the casing.
The licensee determined that the primary containment isolation valves would have closed at
the design-basis-accident containment pressure of 40 pounds per square inch; however, many of the valves may not have been properly set up to close against the normally higher
system pressure under some operating conditions. That is, the valves may not have closed
under the highest expected differential pressure of the contained system fluid. Further details
of the concern are in Licensee Event Report 50-373/96-011, dated October 28, 1996, (Accession No. 9611010277).
The licensee determined which valves at the LaSalle County Station were affected and was
able to properly adjust the actuators to account for the discrepancies between the published
values for the diaphragm area and the actual diaphragm area by (1) adjusting the bench set
on the spring to achieve the required closing force and (2) reversing the diaphragm casings
so that the deeper part of the casing was installed on the bottom with the shallower part of
the casing installed on top to prevent the diaphragm from stretching.
IN 96-68 December 19, 1996 The licensee has not identified similar problems on actuators made by other manufacturers, but licensees should be aware of the concern when testing and making adjustments to the
bench set of pneumatic actuators. The proper setup of these actuators is especially
important when the attached valve is used for isolation in a safety-related application.
Licensees may wish to review their valves and actuators for applicability of this information.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Patricia Campbell, NRR
(301) 415-1311 E-mail: plcenrc.gov
David Skeen, NRR
(301) 415-1174 E-mail: dIsenrc.gov
Andrew Dunlop, Rill
(630) 829-9726 E-mail: axd7@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
my b tC~ -I-h
Attachment
IN 96-68 December 19, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-67 Vulnerability of Emergency 12/19/96 All holders of OLs
Diesel Generators to Fuel or CPs for nuclear
Oil/Lubricating Oil Incom- power reactors
patibility
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
OL = Operating License
CP = Construction Permit
IN 96-68 December 19, 1996 The licensee has not identified similar problems on actuators made by other manufacturers, but licensees should be aware of the concern when testing and making adjustments to the
bench set of pneumatic actuators. The proper setup of these actuators is especially
important when the attached valve is used for isolation in a safety-related application.
Licensees may wish to review their valves and actuators for applicability of this information.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
signed by
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Patricia Campbell, NRR
(301) 415-1311 E-mail: plc@nrc.gov
David Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Andrew Dunlop, Rill
(630) 829-9726 E-mail: axd7@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
Tech Editor has reviewed and concurred on 11/08/96
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: 96-68.IN
To receive a copy of this document, indicate In the box: 'C' = Copy w/o
attachmentlenclosure 'E' = Copy w/attachment/enclosure 'N' = No copy
OFFICE TECH CONTS C/PECB:DRPM D/DRPM,,,----
NAME PCampbell* AChaffee TMa/n
DSkeen*
ADunlop*
DATE 12/05/96 12/12/96 12/II/96 OFFICIAL RECORD COPY
OFFICIAL RECORD COPY
IN 96-XX
December XX, 1996 The licensee has not identified similar problems on actuators made by other manufacturers, but licensees should be aware of the concern when testing and making adjustments to the
bench set of pneumatic actuators. The proper setup of these actuators is especially
important when the attached valve is used for isolation in a safety-related application.
Licensees may wish to review their valves and actuators for applicability of this information.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Patricia Campbell, NRR
(301) 415-1311 E-mail: plc@nrc.gov
David Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Andrew Dunlop, RIII
(630) 829-9726 E-mail: axd7@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC J PECB:DRPM Region IlIl EMEB:DE C/EMEB:DE C/PECB:DRPM
NAME DSkeen* ADunlop* PCampbell* RWessman* AChaffee &
DATE__ 12/05/96 J11/27/96 111/21/96 11/22/96 112/96 Ho~
-
OFC ID/DRPM I /44 NAME TMartin
DATE 112/ /96
[OFFICIAL RECORD COPY]
DOCUMENT NAME: G:XDLS\IN96-AOV.EDA
IN 96-XX
December XX, 1996 The licensee has not identified similar problems on actuators made by other manufacturers, but licensees should be aware of the concern when testing and making adjustments to the
bench set of pneumatic actuators. The proper setup of these actuators is especially/
important when the attached valve is used for isolation in a safety-related application.
Licensees may wish to review their valves and actuators for applicability of this
information.
This information notice requires no specific action or written response. If you ye any
questions about the information in this notice, please contact one of the tec 6ical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) roject manager.
Thomas T. Martin, Dire or
Division of Reactor Pr gram Management
Office of Nuclear R ctor Regulation
Technical contacts: Patricia Campbell, NRR
(301) 415-1311 E-mail: plc@nrc.gov
David Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Andrew Dunlop, Rill
(630) 829-9726 E-mail: axd7@nrc.g
Attachment: List of Recently Iss d NRC Information Notices
OFC PECB:DRPM 1 IIon II EMEB:DE C/EMEB:DE C/PECB:DRPM
NAME D. Ske P. Campbell R. Wessman A. Chaffee
DATE j/AI5196 ' / 1,4t96 Ii/I,21/96 1/tf C96 f / /96 OFC I D/DRPM/
NAME _T. rtin
DATE l //96
[OFFICIAL/RECORD COPY]
DOCUMNT NAME: IN96-AOV.EDA
IN 96-XX
November XX, 1996 The licensee has not identified similar problems on actuators made by other manufacturers, but licensees should be aware of the concern when testing and making adjustments to the
bench set of pneumatic actuators. The proper setup of these actuators is especially
important when the attached valve is used for isolation in a safety-related application.
Licensees may wish to review their valves and actuators for applicability of this
information.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
Thomas T. Martin, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contacts: Patricia Campbell, NRR
(301) 415-1311 E-mail: plc@nrc.gov
David Skeen, NRR
(301) 415-1174 E-mail: dls@nrc.gov
Andrew Dunlop, Rill
(630) 829-9726 E-mail: axd7@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OFC PECB:DRPM Region III EMEB:Dt--, C/EMEB:DE C/PECB:DRPM
NAME D. Skee A.Dun14A IP. Campbell R. W A. Chaffee
DATE // a/296 i /A796 VI' II 0//96 I 7N96 / /96 OFC I D/DRPM
NAME T. Martin
DATE / /96
[OFFICIAL RECORD COPY]
DOCUMENT NAME: IN96-AOV.EDA
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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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