Incident-Reporting Requirements Involving Intakes, During a 24-Hour Period That May Cause a Total Effective Dose Equivalent in Excess of 0.05. Sv (5 Rem)ML031050565 |
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: |
10/30/1996 |
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From: |
Cool D, Martin T NRC/NMSS/IMNS, Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-96-057, NUDOCS 9610230239 |
Download: ML031050565 (7) |
|
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 MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, DC 20555 October 30, 1996 NRC INFORMATION NOTICE 96-57: INCIDENT-REPORTING REQUIREMENTS
INVOLVING INTAKES, DURING A 24-HOUR
PERIOD THAT MAY CAUSE A TOTAL EFFECTIVE
DOSE EQUIVALENT IN EXCESS OF 0.05 Sv
(5 rem)
Addressees
All U.S. Nuclear Regulatory Commission licensees.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to remind
recipients of certain incident notification requirements found in 10 CFR 20.2202(b)(1)(i)
relating to intakes received during a 24-hour period that may cause a Total Effective Dose
Equivalent (TEDE) in excess of 0.05 Sv (5 rem). It is expected that recipients will review the
information for applicability to their facilities, to ensure that this information is considered
when making a decision about the reporting of a radiation exposure incident. However, this
information notice does not contain NRC requirements; therefore, no specific action nor
written response is required.
DescriDtion of Circumstances
Recently, NRC was informed of, and responded to, two incidents involving phosphorus-32 (P-32) and the resulting internal contamination of individuals at biomedical research facilities.
P-32 is a radioisotope widely used in research institutions, as are many other radionuclides.
Although only one of these events raised a question associated with reporting requirements
and is discussed below, our concerns regarding reporting of incidents involving internal
exposure extend to all facilities using licensed material.
On October 16, 1995, a licensee informed the NRC that an incident involving internal
contamination of a researcher had occurred at its facility almost two months earlier. The
licensee's final evaluation of the TEDE received by the individual was 0.048 Sv (4.8 rem)
which was within 5 percent of the annual limit of 0.05 Sv (5 rem). An NRC Incident
Investigation Team analysis (NUREG-1535, "Ingestion of Phosphorus-32 at Massachusetts
Institute of Technology, Cambridge, Massachusetts, Identified on August 19, 1996")
concluded that the licensee's final dose assessment was appropriate, but further concluded
PbR'I ItiDoll %90,y%6103o i )
9610230239 uPcb6,)ccl F) +-H e C-
IN 96-57 October 30, 1996 that data available within the first week was sufficient to indicate that the event threatened to
cause an individual to receive a TEDE in excess of 0.05 Sv (5 rem). Licensee officials told
NRC staff that they had not reported the incident earlier because their analysis indicated that
the researchers TEDE received during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> did not require reporting, pursuant
to 10 CFR 20.2202(b)(1)(i).
The pertinent rule, 10 CFR 20.2202(b)(1)(i), states "...each licensee shall, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of
discovery of the event, report any event involving loss of control of licensed material
possessed by the licensee that may have caused, or threatens to cause, any of the following
conditions:
(1) An individual to receive, in a period of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s- (i) A total effective dose equivalent exceeding 5 rem (0.05 Sv);or..."
The licensee had interpreted this to mean that the dose actually received by the individual
during the particular 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the event had to exceed 0.05 Sv (5 rem) before the
24-hour notification was required. This interpretation is not consistent with the definitions of
TEDE, committed effective dose equivalent (CEDE), and committed dose equivalent (CDE) in
10 CFR 20.1003.
Discussion
As noted above 10 CFR 20.2202(b)(1)(i) requires 24-hour notification if a loss of control of
licensed material may have caused, or threatens to cause, an individual to receive, in a
period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a TEDE exceeding 0.05 Sv (5 rems). NRC's interpretation of the rule is
derived from the definitions in 10 CFR 20.1003 as follows: TEDE is defined as the sum of
the deep-dose equivalent (for external exposures) and the CEDE (for internal exposures),
CEDE is the sum of the products of the weighing factors applicable to each of the body
organs or tissues that are irradiated and the CDE to these organs or tissues, and CDE
means the dose equivalent to organs or tissues of reference that will be received from an
intake of radioactive material by an individual during the 50-year period following the intake.
Licensees are required by 10 CFR 20.2202(b)(1)Qi) to report the TEDE received by an
individual that is based on all doses received during the 24-hour period, including committed
doses (i.e., the CEDE) and not just the doses delivered during the 24-hour period. For
internal doses, the 24-hour period specified in 10 CFR 20.2202(b)(1) refers to the period of
intake and not the period of dose delivery. In the case described above, the CEDE from the
intake received during the event (in a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) threatened to exceed 0.05 Sv
(5 rem). Because this case does not involve external exposure (rather, only ingestion),
CEDE is equal to TEDE. In such a case, a licensee would be required by 10 CFR
20.2202(b)(1)(i) to notify NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of discovery of the event.
IN 96-57 October 30, 1996 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 contacts listed
below or the appropriate regional office.
-' AtJa 1/f4r L-
Thomas T. Martin, Director Donald A. Cool, Director
Division of Reactor Program Management Division of Industrial and
Office of Nuclear Reactor Regulation Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Cynthia G. Jones, NMSS
(301) 415-7853 Email: cgj~nrc.gov
James E. Wigginton, NRR
(301) 415-1059 Email: jew2@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
Are'4"' f (11; I d4-1 -7TAgkc-
- IN 96-57 October 30, 1996 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 contacts listed
below or the appropriate regional office.
original signed by original signed by
Thomas T. Martin, Director Donald A. Cool, Director
Division of Reactor Program Management Division of Industrial and
Office of Nuclear Reactor Regulation Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Cynthia G. Jones, NMSS
(301) 415-7853 Email: cgj@nrc.gov
James E. Wigginton, NRR
(301) 415-1059 Email: jew2@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: 96-57.IN
To receive a cony of this document. hIlicate hI the box: C' - Copy without attachment/enclosure _-E - Copy with attachment/enclosure 'N- - No copy
lOFFICEITECH CONTS L :/PECB I D:DlR l D:IMNS,/
NAME CJones K kV, AChaffee* TMtin' Do
JWigginton* __
DATE 10/24/96 10/28/96 100Y96 104o/ 9 6 OFFICIAL RECORD COPY
IN 96-57 October 29, 1996 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 contacts listed
below or the appropriate regional office.
Thomas T. Martin, Director Donald A. Cool, Director
Division of Reactor Program Management Division of Industrial and
Office of Nuclear Reactor Regulation Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contacts: Cynthia G. Jones, NMSS
(301) 415-7853 Email: cgj@nrc.gov
James E. Wigginton, NRR
(301) 415-1059 Email: jew2@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRR Information Notices
DOCUMENT NAME: 96-57.INa. 'N' - No copy
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OFFICETECH CONTS C:/PECB D:DRPMS
NAME CJones AChaffee TMartin DCool
JWigginton A6f-C /
DATE 1 0t46 aV- 10/,;l6 101 /96 101 196 OFFICIAL RECORD COPY
Attachment 1 IN 96-57 October 30, 1996 Page 1 of I
LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-54 Vulnerability of Stainless 10/17/96 All material licensees
Steel to Corrosion When
Sensitized
96-53 Retrofit to Amersham 660 10/15/96 All industrial radiography
Posilock Radiography licensees
Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility
96-52 Cracked Insertion Rods 09/26/96 All U.S. Nuclear Regulatory
on Troxier Model 3400 Commission portable gauge
Series Portable Moisture licensees and vendors
Density Gauges
96-51 Residual Contamination 09111/96 All material licensees
Remaining in Krypton-85 Handling System After \
Venting
96-47 Recordkeeping, Decommis- 08/19/96 All U.S. Nuclear Regulatory
sioning Notifications for Commission licensees
Disposals of Radioactive
Waste by Land Burial
Authorized Under Former
10 CFR 20.304, 20.302, and Current 20.2002
96-35 Failure of Safety Systems 06/11/96 All U.S. Nuclear Regulatory
on Self-Shielded Irradia- Commission irradiator
tors Because of Inadequate licensees and vendors
Maintenance and Training
K) K)
Attachment 2 IN 96-57 October 3CL,1996 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
96-56 Problems Associated with 01/22/96 All holders of OLs or
Testing, Tuning, or Reset- CPs for nuclear power
ting of Digital Control reactors
Systems While at Power
96-55 Inadequate Net Positive 10/22/96 All holders of OLs or
Suction Head of Emergency CPs for nuclear power
Core Cooling and Contain- reactors
ment Heat Removal Pumps
Under Design Basis Accident
Conditions
96-54 Vulnerability of Stainless 10/17/96 All materials licensees
Steel to Corrosion When
Sensitized
96-53 Retrofit to Amersham 660 10/15/96 All industrial radio- Posilock Radiography graphy licensees
Camera to Correct Incon- sistency in 10 CFR Part 34 Compatibility
95-04, Excessive Cooldown 10/11/96 All holders of OLs or CPs
Supp. I and Depressurization and vendors for nuclear
of the Reactor Coolant power reactors
System Following Loss
of Offsite Power
OL = Operating License
CP = Construction Permit
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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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