Suggested Guidance Relating to Development and Implementation of Corrective ActionML031060071 |
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: |
05/01/1996 |
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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-96-028, NUDOCS 9604290193 |
Download: ML031060071 (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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Category:NRC Information Notice
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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 MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 May 1, 1996 NRC INFORMATION NOTICE 96-28: SUGGESTED GUIDANCE RELATING TO DEVELOPMENT AND
IMPLEMENTATION OF CORRECTIVE ACTION
Addressees
All material and fuel cycle licensees.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to provide addressees with guidance relating to development and
implementation of corrective actions that should be considered after
identification of violation(s) of NRC requirements. It is expected that
recipients will review this information for applicability to their facilities
and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not new NRC requirements;
therefore, no specific action nor written response is required.
Background
On June 30, 1995, NRC revised its Enforcement Policy (NUREG-1600)' 60 FR
34381, to clarify the enforcement program's focus by, in part, emphasizing the
importance of identifying problems before events occur, and of taking prompt, comprehensive corrective action when problems are identified. Consistent with
the revised Enforcement Policy, NRC encourages and expects identification and
prompt, comprehensive correction of violations.
In many cases, licensees who identify and promptly correct non-recurring
Severity Level IV violations, without NRC involvement, will not be subject to
formal enforcement action. Such violations will be characterized as "non- cited" violations as provided in Section VII.B.1 of the Enforcement Policy.
Minor violations are not subject to formal enforcement action. Nevertheless, the root cause(s) of minor violations must be identified and appropriate
corrective action must be taken to prevent recurrence.
If violations of more than a minor concern are identified by the NRC during an
inspection, licensees will be subject to a Notice of Violation and may need to
provide a written response, as required by 10 CFR 2.201, addressing the causes
of the violations and corrective actions taken to prevent recurrence. In some
cases, such violations are documented on Form 591 (for materials licensees)
9604290193^da l~q
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'Copies of NUREG-1600 can be obtained by calling the contacts listed at
the end of the Information Notice.
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IN 96-28 May 1, 1996 which constitutes a notice of violation that requires corrective action but
does not require a written response. If a significant violation is involved, a predecisional enforcement conference may be held to discuss those actions.
The quality of a licensee's root cause analysis and plans for corrective
actions may affect the NRC's decision regarding both the need to hold a
predecisional enforcement conference with the licensee and the level of
sanction proposed or imposed.
Discussion
Comprehensive corrective action is required for all violations. In most
cases, NRC does not propose imposition of a civil penalty where the licensee
promptly identifies and comprehensively corrects violations. However, a
Severity Level III violation will almost always result in a civil penalty if a
licensee does not take prompt and comprehensive corrective actions to address
the violation.
It is important for licensees, upon identification of a violation, to take the
necessary corrective action to address the noncompliant condition and to
prevent recurrence of the violation and the occurrence of similar violations.
Prompt comprehensive action to improve safety is not only in the public
Interest, but is also in the interest of licensees and their employees. In
addition, it will lessen the likelihood of receiving a civil penalty. Compre- hensive corrective action cannot be developed without a full understanding of
the root causes of the violation.
Therefore, to assist licensees, the NRC staff has prepared the following
guidance, that may be used for developing and implementing corrective action.
Corrective action should be appropriately comprehensive to not only prevent
recurrence of the violation at issue, but also to prevent occurrence of
similar violations. The guidance should help in focusing corrective actions
broadly to the general area of concern rather than narrowly to the specific
violations. The actions that need to be taken are dependent on the facts and
circumstances of the particular case.
The corrective action process should involve the following three steps:
1. Conduct a complete and thorough review of the circumstances that led to
the violation. Typically, such reviews include:
Interviews with individuals who are either directly or indirectly
involved in the violation, including management personnel and those
responsible for training or procedure development/guidance.
Particular attention should be paid to lines of communication
between supervisors and workers.
Attachment 1 IN 96-28 May 1, 1996 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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.
95-55 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
12i Bronchial Catheter Afterloader (HDR) Licensees.
Clamping Adapters
95-44 Ensuring Combatible Use of 09/26/95 All Radiography Licensees.
Drive Cables Incorporating
Industrial Nuclear Company
Ball-type Male Connectors
Attachment 2 IN 96-28 May 1, 1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
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
96-23 Fires in Emergency Diesel 04/22/96 All holders of OLs or CPs
Generator Exciters During for nuclear power reactors
Operation Following Unde- tected Fuse Blowing
96-22 Improper Equipment Set- 04/11/96 All holders of OLs or CPs
tings Due to the Use of for nuclear power reactors
Nontemperature-Compensated
Test Equipment
96-21 Safety Concerns Related 04/10/96 All U.S. NRC Medical to the
to the Design of the Door Licensees authorized to use
Interlock Circuit on brachytherapy sources in
Nucletron High-Dose Rate high- and pulsed-dose-rate
and Pulsed Dose Rate remote afterloaders
Remote Afterloading
Brachytherapy 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
OL - Operating License
CP = Construction Permit
IN 96-28 May 1, 1996 Tours and observations of the area where the violation occurred, particularly when those reviewing the incident do not have day-to- day contact with the operation under review. During the tour, individuals should look for items that may have contributed to the
violation as well as those items that may result in future
violations. Reenactments (without use of radiation sources, if they
were involved in the original incident) may be warranted to better
understand what actually occurred.
Review of programs, procedures, audits, and records that relate
directly or indirectly to the violation. The program should be
reviewed to ensure that its overall objectives and requirements are
clearly stated and implemented. Procedures should be reviewed to
determine whether they are complete, logical, understandable, and
meet their objectives (i.e., they should ensure compliance with the
current requirements). Records should be reviewed to determine
whether there is sufficient documentation of necessary tasks to
provide an auditable record and to determine whether similar
violations have occurred previously. Particular attention should be
paid to training and qualification records of individuals involved
with the violation.
2. Identify the root cause of the violation.
Corrective action is not comprehensive unless it addresses the root
cause(s) of the violation. It is essential, therefore, that the root
cause(s) of a violation be identified so that appropriate action can be
taken to prevent further noncompliance in this area, as well as other
potentially affected areas. Violations typically have direct and
indirect cause(s). As each cause is identified, ask what other factors
could have contributed to the cause. When it is'no longer possible to
identify other contributing factors, the root causes probably have been
identified. For example, the direct cause of a violation may be a
failure to follow procedures;'the indirect causes may be inadequate
training, lack of attention to detail,' and inadequate time to carry out
an activity. These factors may have been caused by a lack of staff
resources that, in turn, are indicative of lack of management support.
Each of these factors must be addressed before corrective action is
considered to be comprehensive.
IN 96-28 May 1, 1996 3. Take prompt and comprehensive corrective action that will address the
immediate concerns and prevent recurrence of the violation.
It is important to take immediate corrective action to address the
specific findings of the violation. For example, if the violation was
issued because radioactive material was found in an unrestricted area, immediate corrective action must be taken to place the material under
licensee control in authorized locations. After the immediate safety
concerns have been addressed, timely action must be taken to prevent
future recurrence of the violation. Corrective action is sufficiently
comprehensive when corrective action is broad enough to reasonably
prevent recurrence of the specific violation as well as prevent similar
violations.
In evaluating the root causes of a violation and developing effective
corrective action, consider the following:
1. Has management been informed of the violation(s)?
2. Have the programmatic implications of the cited violation(s) and the
potential presence of similar weaknesses in other program areas been
considered in formulating corrective actions so that both areas are
adequately addressed?
3. Have precursor events been considered and factored into the corrective
actions?
4. In the event of loss of radioactive material, should security of
radioactive material be enhanced?
5. Has your staff been adequately trained on the applicable requirements?
6. Should personnel be re-tested to determine whether re-training should be
emphasized for a given area? Is testing adequate to ensure
understanding of requirements and procedures?
7. Has your staff been notified of the violation and of the applicable
corrective action?
8. Are audits sufficiently detailed and frequently performed? Should the
frequency of periodic audits be increased?
IN 96-28 May 1, 1996 9. Is there a need for retaining an independent technical consultant to
audit the area of concern or revise your procedures?
10. Are the procedures consistent with current NRC requirements, should they
be clarified, or should new procedures be developed?
11. Is a system in place for keeping abreast of new or modified NRC
requirements?
12. Does your staff appreciate the need to consider safety in approaching
daily assignments?
13. Are resources adequate to perform, and maintain control over, the
licensed activities? Has the radiation safety officer been provided
sufficient time and resources to perform his or her oversight duties?
14. Have work hours affected the employees' ability to safely perform the
job?
15. Should organizational changes be made (e.g., changing the reporting
relationship of the radiation safety officer to provide increased
independence)?
16. Are management and the radiation safety officer adequately involved in
oversight and implementation of the licensed activities? Do supervisors
adequately observe new employees and difficult, unique, or new
operations?
17. Has management established a work environment that encourages employees
to raise safety and compliance concerns?
18. Has management placed a premium on production over compliance and
safety? Does management demonstrate a commitment to compliance and
safety?
19. Has management communicated its expectations for safety and compliance?
20. Is there a published discipline policy for safety violations, and are
employees aware of it? Is it being followed?
J I 1s - Se I
K)
IN 96-28 May 1, 1996 This information notice requires no specific action nor written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below.
g('
I-I-/ 7/ (>
A _
Eli zaeth Q. Eyck, Di ctor Doriald A. Cool, Director
Div ion of Fuel Cycle Safety Di%vision of Industrial
and Safeguards atnd Medical Safety
Office of Nuclear Material Safety Off'ice of Nuclear Material Safety
and Safeguards aand Safeguards
Technical contacts: Nader L. Mamish, OE Daniel J. Holody, RI
(301) 415-2740 (610) 337-5312 Internet:nlm@nrc.gov Internet:djh~nrc.gov
Bruno Uryc, Jr., RII Bruce L. Burgess, RIII
(404) 331-5505 (708) 829-9666 Internet:bxu@nrc.gov Internet:blb@nrc.gov
Gary F. Sanborn, RIV
(817) 860-8222 Internet:gfs@nrc.gov
-Attachments:
Stb do
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
1.
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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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