Recent Failures of Control Used on Amersham Model 660 Posilock Radiography SystemsML031050007 |
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: |
12/31/1997 |
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From: |
Cool D NRC/NMSS/IMNS |
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To: |
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References |
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IN-97-091, NUDOCS 9712310254 |
Download: ML031050007 (9) |
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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>. |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 December 31, 1997 NRC INFORMATION NOTICE 97-91: RECENT FAILURES OF CONTROL CABLES USED ON
AMERSHAM MODEL 660 POSILOCK RADIOGRAPHY
SYSTEMS
Addressees
All industrial radiography licensees.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to alert
addressees to potential failures of control (drive) cables used on Amersham Model 660
Posilock radiography systems. It is expected that recipients will review this information for
applicability to their radiographic equipment and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not
NRC requirements; therefore, no specific action nor written response is required.
Description of Circumstances
Recently, NRC became aware of several instances where the control cables used on
Amersham Model 660 Posilock radiography systems became disconnected from the source
assemblies. In each instance, the control cable broke at the male end of the control cable, and
emergency procedures were implemented to return the source to the fully shielded and secured
position. Three recent cases are described below:
Case 1: On November 16, 1997, a licensee was performing routine radiographic operations at
a temporary job site. At the completion of the ninth radiographic exposure, the radiographer
attempted to retract the source assembly into the radiography camera, using the remote drive
assembly. The radiographer observed that his survey meter reading did not change as
expected as the control cable was being retracted. Furthermore, the radiographer noted that
the self-locking mechanism on the radiography camera had not actuated. The radiographer
operated the remote drive assembly again, but did not succeed in returning the source
assembly to the fully shielded and secured position. The radiographer and his assistant then
implemented emergency procedures, maintained control of the area, and contacted their
radiation safety officer (RSO). The RSO responded to the temporary job site and successfully
recovered the source assembly, placing it into an Amersham 650L source changer. The
licensee then reported the source disconnect to the NRC Operations Center. The licensee also
submitted a 30-day report to the NRC.
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-IN 97-91 December31, 1997 Case 2: On December 8, 1997, this same licensee reported another source disconnect, also at
a temporary job site, where the control cable failed in the same manner. In this instance, an
Amersham representative retrieved the disconnected source assembly. The licensee reported
the source assembly disconnect on the same day of the event. In addition to these two source
disconnects, this licensee reported to NRC that it had two previous source assembly
disconnects on Amersham Model 660 Posilock radiography systems, both having similar
failures of the control cable. These disconnects occurred in 1995 and 1996.
Case 3: On November 21, 1997, another licensee was performing routine radiographic
operations at a temporary job site. The radiographers noted that the source assembly had not
retracted to the fully shielded and secured position, implemented emergency procedures, and
notified their RSO. The RSO and a former RSO responded to the temporary job site and
successfully recovered the source assembly, returning it to the radiography camera. The
control cable failed in a similar manner to the previous two cases. Normal operations were
resumed using another control cable. The licensee did not report the source disconnect to the
NRC Operations Center within the 24-hour timeframe, as required by 10 CFR 30.50(b)(2), but
did submit a 30-day report.
Discussion
In all the cited cases, the control cable failed at a point approximately 0.33 - 1.25 centimeter
(0.125 - 0.5 inch) behind the male connector. The failed equipment from each instance has
been returned to the manufacturer for failure analysis. A metallurgical analysis has been
completed on two of the control cables with the results indicating failure from fatigue and failure
due to corrosion and/or fatigue. The cause of the remaining failures is still under investigation
by the manufacturer. Due to these failures, it is recommended that the control cable be
carefully checked before each day's use and during the quarterly maintenance checks, as
required by 10 CFR 34.31 (a) and (b), for indications of corrosion, metal fatigue, or other early
indications of cable failure. It is important to note that these control cables can be purchased
off-the-shelf and may be used on radiography systems manufactured by various companies, and, therefore, these failures may not be limited to control cables used on Amersham
Model 660 Posilock radiography systems.
Each of the source disconnects discussed above required the radiographers to implement
emergency procedures to return the source assembly to the fully shielded and secured position.
Implementation of emergency procedures is crucial to successful source assembly retrieval as
well as to ensuring that exposure of radiographers and members of the public remain as low as
is reasonably achievable. In all three cases, after identifying that the source assembly had
become disconnected from the control cable, the radiographers adequately secured and
controlled the area surrounding the disconnected source assemblies. In addition, the
exposures to the individuals involved in the source assembly retrievals were well within
regulatory limits. Therefore, it is important to implement and adhere to emergency procedures
when source assembly disconnects are identified.
IN 97-91 December 31, 1997 A source assembly disconnect on the Amersham Model 660 radiography system can be
identified by two methods. First, upon completion of retracting the control cable, the self-locking
mechanism should engage, revealing a green dot. This can be identified by observing the
indicator (lock slide) on the locking mechanism. Failure of the self-locking mechanism to
engage would cause the red dot to remain visible on the lock slide, thus indicating the source
was not secured in the fully shielded position, although not necessarily indicating a source
assembly disconnect. Second, when the survey to verify that the source assembly has been
returned to its shielded position is performed after each radiographic exposure, as required by
10 CFR 34.49(b), typical dose rates around the radiography camera and the guide tube should
be observed. However, if the dose rates observed are not typical for a fully shielded source
assembly (e.g., the dose rates may be lower if the source assembly remained in the collimator
or the dose rates may be higher if the source assembly is located within the guide tube), then
the situation should be further investigated. Therefore, it is important to use the survey meter
and to pay careful attention to its readings and the self-locking mechanism indicator to identify
circumstances that are not normal.
In cases of unintentional disconnection of the source assembly from the control cable or the
inability to retract the source assembly to its fully shielded and secured position, licensees must
notify NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, pursuant to the regulations in 10 CFR 30.50(b)(2). The notification
must be made to the NRC Operations Center. In addition to making a notification within
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the licensee must also submit a written report to NRC within 30 days, as required by
10 CFR 30.50(c)(2) and 10 CFR 34.101(a). One report can satisfy both of these requirements, but it must include: (1) a description of the equipment problem; (2) cause of each incident, if
known; (3) manufacturer and model number of equipment involved in the incident; (4) place, time, and date of the incident; (5) actions taken to establish normal operations; (6) corrective
actions taken or planned to prevent recurrence; and (7) qualifications of personnel involved in
the incident [10 CFR 34.101(b)]. Additional information on reporting requirements for industrial
radiography licensees can be found in Information Notice 96-04, "Incident Reporting
Requirements for Radiography Licensees.'
Reporting such problems to NRC is important because it provides the opportunity for NRC to
verify that the material has been properly secured and has not been released into the public
domain. If notified early, NRC can help ensure that all necessary regulatory actions are
completed. In addition, NRC reviews this information to determine if trends or generic safety
issues exist that have the potential to cause a significant safety hazard. If a generic safety
issue is identified, those licensees that may be affected will be notified and informed of the
proper actions to reduce or eliminate similar incidents in the future and to protect the health and
safety of both the occupational workers and the public. It is important to point out that these
failures have not been identified as a generic safety issue at this point in time, but that the
recommendations provided in this information notice should be considered by those licensees
who use Amersham Model 660 Posilock radiography systems.
The Commonwealth of Massachusetts (hereafter, Commonwealth) has been informed of all the
cases discussed above and is working with Amersham on the determination of whether these
- 'IN97-91 December31, 1997 failed control cables represent a generic safety issue. NRC will coordinate with the
Commonwealth to determine if any actions are necessary, based on the findings from the
failure analyses being performed by Amersham.
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.
onal . Cool, ctor
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Larry W. Camper, NMSS
301-415-7231 E-mail: Iwc@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
S Le' St'- D-rkl
-
Attachment 1 IN 97-91 December 31, 1997 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-89 Distribution of Sources and 12/29/97 All sealed source and device
Devices Without Authorization manufacturers and distributors
97-87 Second Retrofit to Industrial 12/12/97 All industrial radiography
Nuclear Company IR100 licensees
Radiography Camera, to
Correct Inconsistency in
10 CFR Part 34 Compatibility
97-86 Additional Controls for Transport 12/12/97 Registered users of the Model
of the Amersham Model No. 660 No. 660 series packages, and
Series Radiographic Exposure Nuclear Regulatory Commission
Devices industrial radiography licensees
97-75 Enforcement Sanctions Issued 09/24197 All U.S. Nuclear Regulatory
as a Result of Deliberate Commission licensees
Violations of NRC Requirements
97-72 Potential for Failure 09/22/97 All holders of OLs or CPs
of the Omega Series for nuclear power reactors
Sprinkler Heads and fuel cycle facilities
97-65 Failures of High-Dose- 08/15/97 All high-dose-rate remote
Rate Remote Afterloading afterloader licensees
Device Source Guide Tubes, Catheters, and Applicators
97-64 Potential Problems 08/13/97 All U.S. Nuclear Regulatory
Associated with Loss Commission medical tele- of Electrical Power therapy licensees
in Certain Teletherapy
Units
97-61 U.S. Department of 08/06/97 All U.S. Nuclear Regulatory
Health and Human Commission medical
Services Letter, to licensees, veterinarians, Medical Device Manu- and manufacturers/distri- facturers, on the butors of medical devices
Year 2000 Problem
I
Attachment 2 IN 97-91 December 31, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-90 Use of Nonconservative 12/30197 All holders of OLs for nuclear
Acceptance Criteria in power reactors except those
Safety-Related Pump who have ceased operations
Surveillance Tests and have certified that fuel has
been permanently removed from
the vessel
97-89 Distribution of Sources and 12/29/97 All sealed source and device
Devices Without Authorization manufacturers and distributors
97-88 Experiences During Recent 12/16/97 All holders of OLs for pressurized- Steam Generator Inspections water reactors except those who
have permanently ceased
operations and have certified that
fuel has been permanently
removed from the reactor
97-87 Second Retrofit to 12/12/97 All industrial radiography
Industrial Nuclear Company licensees
IR 100 Radiography Camera, to Correct Inconsistency in
10 CFR Part 34 Compatibility
97-86 Additional Controls for 12/12/97 Registered users of the Model
Transport of the Amersham No. 660 series packages, and
Model No. 660 Series Nuclear Regulatory Commission
Radiographic Exposure Devices industrial radiography licensees
97-85 Effects of Crud Buildup 12/11/97 All holders of OLs for pressurized- and Boron Deposition on water reactors, except those
Power Distribution and licensees who have permanently
Shutdown Margin ceased operations and have
certified that the fuel has been
permanently removed from the
reactor vessel
OL = Operating License
CP = Construction Permit
IN97-XX
December XX, 1997 Commonwealth to determine if any actions are necessary, based on the findings from the
failure analyses being performed by Amersham.
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.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Larry W. Camper, NMSS
301-415-7231 E-mail: LWC@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: c:UtN97-XX.BWS
l OFC l SSSS . Tech Editor I SSS3 lLJ Ij -J0 l
NAME BSmi&L EKraus//EK SBaggett a er/LC UVC
DATE 12/I19712118/97 12/ /97 1 __7 __2__9 OFFICIAL RECORD COPY 2A
IN 97-XX
December XX, 1997 cables represent a generic safety issue. The NRC will coordinate with the Commonwealth to
determine if any actions are necessary based upon the findings from the failure analyses being
performed by Amersham.
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.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Larry W. Camper, NMSS
301-415-7231 E-mail: LWC@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: c:\IN97-XX.BWS
IOFC I SSSS I Tech Editor Ill SSSS I li IMNSI
NAME BSmith EKraus SBaggett *Mpr DCool
DATE 12/ /97 12/ /97 12/ /1 9 7 12/ /97 OFFICIAL RECORD COPY
~ 6 97-91 December31, 1997 failed control cables represent a generic safety issue. NRC will coordinate with the
Commonwealth to determine if any actions are necessary, based on the findings from the
failure analyses being performed by Amersham.
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.
Donald A. Cool, Director
Division of Industrial and
Medical Nuclear Safety
Office of Nuclear Material Safety
and Safeguards
Technical contact: Larry W. Camper, NMSS
301-415-7231 E-mail: lwc@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information Notices
2. List of Recently Issued NRC Information Notices
DOCUMENT NAME: 97-91.1N
I SSSS Tech Editor I Ss l Il IMNS
NAME BSmith//BS EKraus//EK SBaggett LCamper//LC DCool
DATE 12/22/97 12/18/97 12/ /97 12/18/97 12/30/97 OFFICIAL RECORD COPY
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
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